Systematic comparison of ISOLDE-SC yields with calculated in-target production rates
International Nuclear Information System (INIS)
Recently, a series of dedicated inverse-kinematics experiments performed at GSI, Darmstadt, has brought an important progress in our understanding of proton and heavy-ion induced reactions at relativistic energies. The nuclear reaction code ABRABLA that has been developed and benchmarked against the results of these experiments has been used to calculate nuclide production cross sections at different energies and with different targets and beams. These calculations are used to estimate nuclide production rates by protons in thick targets, taking into account the energy loss and the attenuation of the proton beam in the target, as well as the low-energy fission induced by the secondary neutrons. The results are compared to the yields of isotopes of various elements obtained from different targets at CERN-ISOLDE with 600 MeV protons, and the overall extraction efficiencies are deduced. The dependence of these extraction efficiencies on the nuclide half-life is found to follow a simple pattern in many different cases. A simple function is proposed to parameterize this behavior in a way that quantifies the essential properties of the extraction efficiency for the element and the target - ion-source system in question. (orig.)
In-target yields for RIB production with EURISOL
International Nuclear Information System (INIS)
EURISOL DS (European Isotope Separation On-Line - Design Study) project is the European common effort in planning a next generation RIB factory able to deliver secondary beams up to 1013 pps at energies up to 150 MeV u-1. The proposed schematic layout of the facility is based on four target stations, three direct targets of 100kW of beam power and one multi-MW (MMW) target two stages assembly. Being produced via spallation the RIBs produced in the direct targets are mainly proton rich. While in the multi-MW target high intensity RIBs of neutron rich isotopes are produced by fission in actinide targets placed in the fast neutron spectrum given by a liquid metal spallation source. The purpose of this paper is to summarize a work carried out within Task 11 'Beam Intensity Calculations': estimation of the in-target yield intensities produced in the various target configurations. Benchmark studies were performed initially in order to verify the accurate description of the spallation models used by the MCNPX2.5.0 code and to choose the best options to be used for the present work requirements. Numerous calculations using MCNPX2.5.0 combined with the evolution code CINDER'90 were carried out to assess the performance of the direct targets. The production rates in the case of the MMW-fission targets were obtained with a given and fixed geometry (optimized to reach 1015 fission s-1). Only fissile material, moderator and reflector were free. (author)
Calculation of Hilbert Borcherds Products
Mayer, Sebastian
2010-01-01
In Brunier and Bundschuh, “On Borcherds Products Associated with Lattices of Prime Discriminant.” Ramanujan Journal 7 (2003), 49–61, the authors use Borcherds lifts to obtain Hilbert modular forms. Another approach is to calculate Hilbert modular forms using the Jacquet--Langlands correspondence, which was implemented by Lassina Dembele in "Magma". In Mayer, "Rings of Hilbert Modular Forms for the Fields $\\Q(\\sqrt{13})$ and $\\Q(\\sqrt{17})$,'' To appear, 2009, we use Brunier and...
Optimization of in-target yields for RIB production: Part 1: direct targets
International Nuclear Information System (INIS)
In the framework of the EURISOL-DS project and within Task-11, we have performed in-target yield calculations for different configurations of thick direct targets. The target materials tested are Al2O3, SiC, Pb(molten), Ta and UC3. The target was irradiated with protons of 0.5, 1.0, 1.5 and 2.0 GeV. The production rates have been computed using the MCNPX transport/generation code, coupled with the CINDER-90 evolution program. The yield distributions as a function of charge number Z and mass number A have been evaluated. Their production rates have been optimized for 11 selected elements (Li, Be, Ne, Mg, Ar, Ni, Ga, Kr, Hg, Sn and Fr) and 23 of their isotopes of interest. Finally, the isotopic distributions for each of these 11 elements have been optimized in terms of the target material, its geometry, and incident proton energy
Calculation code of the fission products activity
International Nuclear Information System (INIS)
The document describes the two codes for the calculation of the fission products activity. The ''Pepin le bref'' code gives the exact value of the beta and gamma activities of completely known fission products. The code ''Plus Pepin'' introduces the beta and gamma activities whose properties are partially known. (A.L.B.)
Product Analysis in Target Market : Potential of Chinese Electric Motorcycle in Southern Finland
Ye, Jing
2012-01-01
Ye, Jing 2012. Product Analysis in Target Market. Potential of Chinese Electric Motorcycle in Southern Finland. Bachelor’s Thesis. Kemi-Tornio University of Applied Sciences. Business and Culture. Pages 61. The thesis investigates potential of Chinese electric motorcycles in Southern Finland market through a product analysis. The objective of the thesis is to understand market situation and search market potential of Chinese electric motorcycles through a product analysis. The target marke...
Model for fission-product calculations
International Nuclear Information System (INIS)
Many fission-product cross sections remain unmeasurable thus considerable reliance must be placed upon calculational interpolation and extrapolation from the few available measured cross sections. The vehicle, particularly for the lighter fission products, is the conventional optical-statistical model. The applied goals generally are: capture cross sections to 7 to 10% accuracies and inelastic-scattering cross sections to 25 to 50%. Comparisons of recent evaluations and experimental results indicate that these goals too often are far from being met, particularly in the area of inelastic scattering, and some of the evaluated fission-product cross sections are simply physically unreasonable. It is difficult to avoid the conclusion that the models employed in many of the evaluations are inappropriate and/or inappropriately used. In order to alleviate the above unfortunate situations, a regional optical-statistical (OM) model was sought with the goal of quantitative prediction of the cross sections of the lighter-mass (Z = 30-51) fission products. The first step toward that goal was the establishment of a reliable experimental data base consisting of energy-averaged neutron total and differential-scattering cross sections. The second step was the deduction of a regional model from the experimental data. It was assumed that a spherical OM is appropriate: a reasonable and practical assumption. The resulting OM then was verified against the measured data base. Finally, the physical character of the regional model is examined
Recent PQCD calculations of heavy quark production
Vitev, I
2006-01-01
We summarize the results of a recent study of heavy quark production and attenuation in cold nuclear matter. In p+p collisions, we investigate the relative contribution of partonic sub-processes to $D$ meson production and $D$ meson-triggered inclusive di-hadrons to lowest order in perturbative QCD. While gluon fusion dominates the creation of large angle $D\\bar{D}$ pairs, charm on light parton scattering determines the yield of single inclusive $D$ mesons. The distinctly different non-perturbative fragmentation of $c$ quarks into $D$ mesons versus the fragmentation of quarks and gluons into light hadrons results in a strong transverse momentum dependence of anticharm content of the away-side charm-triggered jet. In p+A reactions, we calculate and resum the coherent nuclear-enhanced power corrections from the final-state partonic scattering in the medium. We find that single and double inclusive open charm production can be suppressed as much as the yield of neutral pions from dynamical high-twist shadowing. ...
10Be production calculations in the atmosphere
International Nuclear Information System (INIS)
Cosmic rays (CRs) interacting with the Earth's atmosphere produce a cascade of secondary particles and cosmogenic nuclides. Cosmogenic nuclides itself are stored in natural archives such as ice cores and can therefore be measured by e.g. accelerator mass spectrometry (AMS). Here we present our calculations of the cosmogenic radionuclide 10Be, which is produced by spallation reactions between secondary neutrons and protons and the atmospheric gases nitrogen and oxygen, using PLANETOCOSMICS, a GEANT4 based computer code (Desorgher[2006]).
Aspects of Costs Calculation in a Vegetable Production Farm
Teodor HADA
2012-01-01
This paper deals with the aspects of the issue of costs calculation for a vegetable production farm in terms of theory and practice. Aspects of the active accounting regulations, applicable to vegetable production farms, are presented in the content. Features of the vegetable production are detailed, and the applicability of costs calculation methods is shown by the example of the “to order” method. In terms of accounting, there are presented the records made in the management accounting, in...
Innovative Product Design Based on Customer Requirement Weight Calculation Model
Institute of Scientific and Technical Information of China (English)
Chen-Guang Guo; Yong-Xian Liu; Shou-Ming Hou; Wei Wang
2010-01-01
In the processes of product innovation and design, it is important for the designers to find and capture customer's focus through customer requirement weight calculation and ranking. Based on the fuzzy set theory and Euclidean space distance, this paper puts forward a method for customer requirement weight calculation called Euclidean space distances weighting ranking method. This method is used in the fuzzy analytic hierarchy process that satisfies the additive consistent fuzzy matrix. A model for the weight calculation steps is constructed;meanwhile, a product innovation design module on the basis of the customer requirement weight calculation model is developed. Finally, combined with the instance of titanium sponge production, the customer requirement weight calculation model is validated. By the innovation design module, the structure of the titanium sponge reactor has been improved and made innovative.
Analytical calculation of heavy quarkonia production processes in computer
Braguta, V. V.; Likhoded, A. K.; Luchinsky, A. V.; Poslavsky, S. V.
2013-01-01
This report is devoted to the analytical calculation of heavy quarkonia production processes in modern experiments such as LHC, B-factories and superB-factories in computer. Theoretical description of heavy quarkonia is based on the factorization theorem. This theorem leads to special structure of the production amplitudes which can be used to develop computer algorithm which calculates these amplitudes automatically. This report is devoted to the description of this algorithm. As an example ...
Calculational techniques (not only) for single top production
WEINZIERL, Stefan
2000-01-01
A next-to-leading order calculation for single top production including spin-dependent observables requires efficient techniques for the calculation of the relevant loop amplitudes. We discuss the adaption of dimensional regularization, the spinor helicity method and of tensor integral reduction algorithms to these needs.
Calorimetric measurement of afterheat in target materials for the accelerator production of tritium
International Nuclear Information System (INIS)
The estimate of afterheat in a spallation target of lead (Pb) or tungsten (W), by calorimetry, is the purpose of this experiment in support of the Accelerator Production of Tritium (APT). Such measurements are needed to confirm code calculations, these being the only practical way of gaining this type of information in a form suitable to aid the design of the APT machine. Knowledge of the magnitude and duration of afterheat resulting from decay of activation products produced by proton bombardment of the target is necessary to quantify APT safety assumptions, to design target cooling and safety systems, and to reduce technical risk. Direct calorimetric measurement of the afterheat for the appropriate incident proton energies is more reliable than the available alternative, which is indirect, based on data from gamma-ray spectroscopy measurements. The basic concept, a direct measurement of decay afterheat which bypasses the laborious classical way of determining this quantity, has been demonstrated to work. The gamma-ray energy given off by the decay products produced in the activation of lead or tungsten with high-energy protons apparently does represent a significant fraction of the total decay energy. A calorimeter designed for measurement of isotopes decaying by alpha emission must be modified to reduce energy lost with escaping gamma rays. Replacement of the aluminum liner with a tungsten liner in the SSC measurement chamber resulted in a 270% increase in measured heat, proving that the energy loss in the earlier (1992) measurements was significant. Gamma-ray measurements are needed to confirm the gamma-ray absorption calculations for the calorimeter to determine the correction for loss of heat due to transmission of high-energy gamma rays through the calorimeter walls. The experiments at BLIP have shown that calorimetry can be a useful tool in measuring the afterheat in APT target materials
Aspects of Costs Calculation in a Vegetable Production Farm
Directory of Open Access Journals (Sweden)
Teodor HADA
2012-11-01
Full Text Available This paper deals with the aspects of the issue of costs calculation for a vegetable production farm in terms of theory and practice. Aspects of the active accounting regulations, applicable to vegetable production farms, are presented in the content. Features of the vegetable production are detailed, and the applicability of costs calculation methods is shown by the example of the “to order” method. In terms of accounting, there are presented the records made in the management accounting, in the financial accounting and also the conclusions to be drawn in terms of management accounting utility in financial decision making.
Shielding calculations for a production target for secondary beams
Energy Technology Data Exchange (ETDEWEB)
Rehm, K.E.; Back, B.B.; Jiang, C.L. [and others
1995-08-01
In order to estimate the amount of shielding required for a radioactive beam facility dose rate were performed. The calculations for production targets with different geometries were performed. The calculations were performed with the MSU shielding code assuming a 500-p{mu}A 200-MeV deuteron beam stopped in a thick Al target. The target and the ion-optical elements for beam extraction are located in a 2 m{sup 3} large volume at the center of the production cell. These dose rate calculations show that with a combination of Fe and concrete it is possible to reduce the dose rate expected at the surface of a 7-m-wide cube housing the production target to less than 2 mrem/hr.
Pulsation Calculation of Cylindrical Underwater Gas Explosion Products in Well
Directory of Open Access Journals (Sweden)
A. M. Sheiko
2014-06-01
Full Text Available The paper considers a mathematical model of pulsation process of cylindrical underwater gas explosion products in the well at gas-impulse regeneration filters. A differential equation of the second-order with constant coefficients has been derived. A special calculation program has been developed to solve the equation. Expressions for calculation of maximum radius of cylindrical explosion chamber at the end of expansion process and pressure impulse in the first half-period pulsation.
Large fragment production calculations in relativistic heavy-ion reactions
International Nuclear Information System (INIS)
The abrasion-ablation model is briefly described and then used to calculate cross sections for production of large fragments resulting from target or projectile fragmentation in high-energy heavy-ion collisions. The number of nucleons removed from the colliding nuclei in the abrasion stage and the excitation energy of the remaining fragments (primary products) are calculated with the geometrical picture of two different models: the fireball and the firestreak models. The charge-to-mass dispersion of the primary products is calculated using either a model which assumes no correlations between proton and neutron positions inside the nucleus (hypergeometric distribution) or a model based upon the zero-point oscillations of the giant dipole resonance (NUC-GDR). Standard Weisskopf--Ewing statistical evaporation calculations are used to calculate final product distributions. Results of the pure abrasion-ablation model are compared with a variety of experimental data. The comparisons show the insufficiency of the extra-surface energy term used in the abrasion calculations. A frictional spectator interaction (FSI) is introduced which increases the average excitation energy of the primary products, and improves the results considerably in most cases. Agreements and discrepancies of the results calculated with the different theoretical assumptions and the experimental data are studied. Of particular relevance is the possibility of observing nuclear ground-state correlations.Results of the recently completed experiment of fragmentation of 213 Mev/A 40Ar projectiles are studied and shown not to be capable of answering that question unambiguously. But predictions for the upcoming 48Ca fragmentation experiment clearly show the possibility of observing correlation effects. 78 references
Calculation of CWKB envelope in boson and fermion productions
Indian Academy of Sciences (India)
S Biswas; I Chowdhury
2007-01-01
We present the calculation of envelope of boson and of both low- and high- mass fermion production at the end of inflation when the coherently oscillating inflatons decay into bosons and fermions. We consider three different models of inflation and use CWKB technique to calculate the envelope to understand the structure of resonance band formation. We observe that though low-mass fermion production is not effective in pre-heating because of Pauli blocking, it is quite probable for high-mass fermion to take part in pre-heating.
Production rate calculations for a secondary beam facility
Energy Technology Data Exchange (ETDEWEB)
Jiang, C.L.; Back, B.B.; Rehm, K.E.
1995-08-01
In order to select the most cost-effective method for the production of secondary ion beams, yield calculations for a variety of primary beams were performed ranging in mass from protons to {sup 18}O with energies of 100-200 MeV/u. For comparison, production yields for 600-1000 MeV protons were also calculated. For light ion-(A < {sup 4}He) induced reactions at energies above 50 MeV/u the LAHET code was used while the low energy calculations were performed with LPACE. Heavy-ion-induced production rates were calculated with the ISAPACE program. The results of these codes were checked against each other and wherever possible a comparison with experimental data was performed. These comparisons extended to very exotic reaction channels, such as the production of {sup 100}Sn from {sup 112}Sn and {sup 124}Xe induced fragmentation reactions. These comparisons indicate that the codes are able to predict production rates to within one order of magnitude.
Calculation of fusion product angular correlation coefficients for fusion plasmas
International Nuclear Information System (INIS)
The angular correlation coefficients for fusion products are calculated in the cases of Maxwellian and beam-target plasmas. Measurement of these coefficients as a localized ion temperature or fast-ion diagnostic is discussed. 8 refs., 7 figs., 1 tab
Calculation of vapor pressure of fission product fluorides and oxyfluorides
International Nuclear Information System (INIS)
The equilibrium diagrams of the condensed phases - solid and liquid - and vapor phase are collected for the principal fluorides and oxyfluorides of fission product elements (atomic number from 30 to 66). These diagrams are used more particularly in fuel reprocessing by fluoride volatility process. Calculations and curves (vapor pressure in function of temperature) are processed using a computer program given in this report
International Nuclear Information System (INIS)
To speed-up the absorbed dose (AD) computation while accounting for tissue heterogeneities, a Collapsed Cone (CC) superposition algorithm was developed and validated for 90Y. The superposition was implemented with an Energy Deposition Kernel scaled with the radiological distance, along with CC acceleration. The validation relative to Monte Carlo simulations was performed on 6 phantoms involving soft tissue, lung and bone, a radioembolisation treatment and a simulated bone metastasis treatment. As a figure of merit, the relative AD difference (ΔAD) in low gradient regions (LGR), distance to agreement (DTA) in high gradient regions and the γ(1%,1 mm) criterion were used for the phantoms. Mean organ doses and γ(3%,3 mm) were used for the patient data. For the semi-infinite sources, ΔAD in LGR was below 1%. DTA was below 0.6 mm. All profiles verified the γ(1%,1 mm) criterion. For both clinical cases, mean doses differed by less than 1% for the considered organs and all profiles verified the γ(3%,3 mm). The calculation time was below 4 min on a single processor for CC superposition and 40 h on a 40 nodes cluster for MCNP (108 histories). Our results show that the CC superposition is a very promising alternative to MC for 90Y dosimetry, while significantly reducing computation time. (paper)
Sanchez-Garcia, Manuel; Gardin, Isabelle; Lebtahi, Rachida; Dieudonné, Arnaud
2014-09-01
To speed-up the absorbed dose (AD) computation while accounting for tissue heterogeneities, a Collapsed Cone (CC) superposition algorithm was developed and validated for 90Y. The superposition was implemented with an Energy Deposition Kernel scaled with the radiological distance, along with CC acceleration. The validation relative to Monte Carlo simulations was performed on 6 phantoms involving soft tissue, lung and bone, a radioembolisation treatment and a simulated bone metastasis treatment. As a figure of merit, the relative AD difference (ΔAD) in low gradient regions (LGR), distance to agreement (DTA) in high gradient regions and the γ(1%,1 mm) criterion were used for the phantoms. Mean organ doses and γ(3%,3 mm) were used for the patient data. For the semi-infinite sources, ΔAD in LGR was below 1%. DTA was below 0.6 mm. All profiles verified the γ(1%,1 mm) criterion. For both clinical cases, mean doses differed by less than 1% for the considered organs and all profiles verified the γ(3%,3 mm). The calculation time was below 4 min on a single processor for CC superposition and 40 h on a 40 nodes cluster for MCNP (108 histories). Our results show that the CC superposition is a very promising alternative to MC for 90Y dosimetry, while significantly reducing computation time.
Nuclear model calculations on cyclotron production of 51Cr
International Nuclear Information System (INIS)
51Cr (T1/2 = 27.7 d), which decays via electron capture (100 %) with 320 keV gamma emission (9.8 %), is a radionuclide with still a large application in biological studies. In this work, ALICE/ASH and TALYS nuclear model codes along with some adjustments are used to calculate the excitation functions for proton, deuteron, α-particle and neutron induced on various targets leading to the production of 51Cr radioisotope. The production yields of 51Cr from various reactions are determined using the excitation function calculations and stopping power data. The results are compared with corresponding experimental data and discussed from point of view of feasibility.
Nuclear model calculations on cyclotron production of {sup 51}Cr
Energy Technology Data Exchange (ETDEWEB)
Kakavand, Tayeb [Imam Khomeini International Univ., Qazvin (Iran, Islamic Republic of). Dept. of Physics; Aboudzadeh, Mohammadreza [Nuclear Science and Technology Research Institute/AEOI, Karaj (Iran, Islamic Republic of). Agricultural, Medical and Industrial Research School; Farahani, Zahra; Eslami, Mohammad [Zanjan Univ. (Iran, Islamic Republic of). Dept. of Physics
2015-12-15
{sup 51}Cr (T{sub 1/2} = 27.7 d), which decays via electron capture (100 %) with 320 keV gamma emission (9.8 %), is a radionuclide with still a large application in biological studies. In this work, ALICE/ASH and TALYS nuclear model codes along with some adjustments are used to calculate the excitation functions for proton, deuteron, α-particle and neutron induced on various targets leading to the production of {sup 51}Cr radioisotope. The production yields of {sup 51}Cr from various reactions are determined using the excitation function calculations and stopping power data. The results are compared with corresponding experimental data and discussed from point of view of feasibility.
Calculations of pair production by Monte Carlo methods
International Nuclear Information System (INIS)
We describe some of the technical design issues associated with the production of particle-antiparticle pairs in very large accelerators. To answer these questions requires extensive calculation of Feynman diagrams, in effect multi-dimensional integrals, which we evaluate by Monte Carlo methods on a variety of supercomputers. We present some portable algorithms for generating random numbers on vector and parallel architecture machines. 12 refs., 14 figs
Calculations of pair production by Monte Carlo methods
Energy Technology Data Exchange (ETDEWEB)
Bottcher, C.; Strayer, M.R.
1991-01-01
We describe some of the technical design issues associated with the production of particle-antiparticle pairs in very large accelerators. To answer these questions requires extensive calculation of Feynman diagrams, in effect multi-dimensional integrals, which we evaluate by Monte Carlo methods on a variety of supercomputers. We present some portable algorithms for generating random numbers on vector and parallel architecture machines. 12 refs., 14 figs.
Cost Accounting Methods and Calculation Agricultural Products` Cost
Saule B. Spatayeva
2015-01-01
In the condition of the current market the effective manage of expenses and calculation accountancy of cost production in agriculture must be aimed to control for resources usage at any level of technology process and getting the accountancy database needed for gaining the management targets.The improving the technologies and set up aspects of business entity activity, taken place for the last decades, which caused a significant influence on condition and structure expenses but could not prov...
Neutron cross section calculations for fission-product nuclei
International Nuclear Information System (INIS)
To satisfy nuclear data requirements for fission-product nuclei, Hauser-Feshbach statistical calculations with preequilibrium corrections for neutron-induced reactions on isotopes of Se, Kr, Sr, Zr, Mo, Sn, Xe, and Ba between 0.001 and 20 MeV. Spherical neutron optical parameters were determined by simultaneous fits to resonance data and total cross sections. Isospin coefficients appearing in the optical potentials were determined through analysis of the behavior of s- and p-wave strengths as a function of mass for a given Z. Gamma-ray strength functions, determined through fits to stable-isotope capture data, were used in the calculation of capture cross sections and gamma-ray competition to particle emission. The resulting (n,γ), (n,n'), (n,2n), and (n,3n) cross sections, the secondary neutron emission spectra, and angular distributions calculated for 19 fission products will be averaged to provide a resulting ENDF-type fission-product neutronics file. 11 references
Energy Technology Data Exchange (ETDEWEB)
Yrjaenaeinen, H.; Silvenius, F.; Kaukoranta, T.; Naekkilae, J.; Saerkkae, L.; Tuhkanen, E.-M.
2013-02-01
This report presents the results of climate impact calculations for five products produced in Finnish greenhouses: tomatoes, cucumbers, salad crops, tulips and Elatior begonias. The study employed 16 greenhouses for the investigation; two greenhouses each for the tulips and the begonias and four each for the tomatoes, cucumbers and salad crops. Based on these calculations a greenhouse gas calculator was developed for greenhouse cultivators. The calculator is available at internet in www.kauppapuutarhaliitto.fi {yields} hiilijalanjaelki. In terms of environmental impacts this study concentrated on the climate impacts of the investigated products, and the calculations were made for the most significant greenhouse gases: carbon dioxide, methane and nitrous oxide. The following processes were included in the system boundaries: plant growing, manufacturing of lime, fertilizers and pesticides, manufacturing and disposal of pots, carbon dioxide production, irrigation, lighting, thermal curtains and cooling systems, the production and use of electricity and heat energy, distribution of products by the growers, other transportation, end-of-life and recycling. Processes excluded from the study were: distribution by other actors, retail functions, the consumer stage, and maintenance and manufacturing of infrastructure. The study used MTT's calculation model for the climate impact of food products excluding distribution and retail processes. The greenhouses selected for the study had some variation in their energy profiles and growing seasons. In addition, scenarios were created for different energy sources by using the average figures from this study. Monthly energy consumption values were also obtained from a number of the greenhouses and these were used to assess the variations in climate impact for different seasons. According to the results of the study the use of energy is the most significant source of climate impact of greenhouse products. In the tomato farms the
Radioisotope production in target fragmentation with high-energy heavy ions at HIMAC
International Nuclear Information System (INIS)
In order to improve utilisation of the multitracer method, two aspects of the method were pursued in this study. The production of radioisotopes from target fragmentation of 197Au nuclei was performed with high-energetic heavy ions of 12C (180, 290, 400 MeV/u) and 40Ar (290, 650 MeV/u) at HIMAC facilities. The yields of products were measured by using a thick-target-thick-catcher method and off-line gamma spectrometry with Ge semiconductor detectors. Besides, a special apparatus for practice of the radioisotope production was designed in application of the tracers for separation of the products from target material with high efficiency and the target material and shape for the design was investigated in a trial examination. (author)
Cost Accounting Methods and Calculation Agricultural Products` Cost
Directory of Open Access Journals (Sweden)
Saule B. Spatayeva
2015-04-01
Full Text Available In the condition of the current market the effective manage of expenses and calculation accountancy of cost production in agriculture must be aimed to control for resources usage at any level of technology process and getting the accountancy database needed for gaining the management targets.The improving the technologies and set up aspects of business entity activity, taken place for the last decades, which caused a significant influence on condition and structure expenses but could not provide the increase of economic effectiveness in agriculture.
Nuclear Structure Measurements of Fermium-254 and Advances in Target Production Methodologies
Gothe, Oliver Ralf
2014-01-01
The Berkeley Gas-filled Separator (BGS) has been upgraded with a new gas control system. It allows for accurate control of hydrogen and helium gas mixtures. This greatly increases the capabilities of the separator by reducing background signals in the focal plane detector for asymmetric nuclear reactions. It has also been shown that gas mixtures can be used to focus the desired reaction products into a smaller area, thereby increasing the experimental efficiency.A new electrodeposition cell h...
A model for fission-product calculations, 1
International Nuclear Information System (INIS)
Many fission-product cross sections remain unmeasurable thus considerable reliance must be placed upon calculational interpolation and exstrapolation from the few available measured cross sections. The vehicle, particularly for the lighter fission products, is the conventional the optical-statistical model. The applied goals generally are: capture cross sections to 7 - 10 % accuracies and inelastic-scattering cross sections to 25 - 50 %. Comparisons of recent evaluations and experimental results indicate that these goals have too often are far from met, particularly in the area of inelastic scattering, and some of the evaluated fission-product cross sections are simply physically unreasonable. An example of these discrepancies is shown in a figure. The evaluated inelastic-scattering cross sections of palladium are nearly a 100 % discrepant with observation and the isotopes are prominent fission products with large inelastic-scattering cross sections at relatively low energies. It is difficult to avoid the conclusion that the models employed in many of the evaluations are inappropriate and/or inappropriately used. (author)
Zamani, M.; Kasesaz, Y.; Khalafi, H.; Pooya, S. M. Hosseini
Boron Neutron Capture Therapy (BNCT) is used for treatment of many diseases, including brain tumors, in many medical centers. In this method, a target area (e.g., head of patient) is irradiated by some optimized and suitable neutron fields such as research nuclear reactors. Aiming at protection of healthy tissues which are located in the vicinity of irradiated tissue, and based on the ALARA principle, it is required to prevent unnecessary exposure of these vital organs. In this study, by using numerical simulation method (MCNP4C Code), the absorbed dose in target tissue and the equiavalent dose in different sensitive tissues of a patiant treated by BNCT, are calculated. For this purpose, we have used the parameters of MIRD Standard Phantom. Equiavelent dose in 11 sensitive organs, located in the vicinity of target, and total equivalent dose in whole body, have been calculated. The results show that the absorbed dose in tumor and normal tissue of brain equal to 30.35 Gy and 0.19 Gy, respectively. Also, total equivalent dose in 11 sensitive organs, other than tumor and normal tissue of brain, is equal to 14 mGy. The maximum equivalent doses in organs, other than brain and tumor, appear to the tissues of lungs and thyroid and are equal to 7.35 mSv and 3.00 mSv, respectively.
Calculation of the spallation product distribution in the evaporation process
International Nuclear Information System (INIS)
Some investigations are performed for the calculational model of nuclear spallation reaction in the evaporation process. A new version of a spallation reaction simulation code NUCLEUS has been developed by incorporating the newly revised Uno ampersand Yamada's mass formula and extending the counting region of produced nuclei. The differences between the new and original mass formulas are shown in the comparisons of mass excess values. The distributions of spallation products of a uranium target nucleus bombarded by energy (0.38 - 2.9 GeV) protons have been calculated with the new and original versions of NUCLEUS. In the fission component Uno ampersand Yamada's mass formula reproduces the measured data obtained from thin foil experiments significantly better, especially in the neutron excess side, than the combination of the Cameron's mass formula and the mass table compiled by Wapstra, et al., in the original version of NUCLEUS. Discussions are also made on how the mass-yield distribution of products varies dependent on the level density parameter a characterizing the particle evaporation. 16 refs., 7 figs., 1 tab
Carbon footprint of Canadian dairy products: calculations and issues.
Vergé, X P C; Maxime, D; Dyer, J A; Desjardins, R L; Arcand, Y; Vanderzaag, A
2013-09-01
The Canadian dairy sector is a major industry with about 1 million cows. This industry emits about 20% of the total greenhouse gas (GHG) emissions from the main livestock sectors (beef, dairy, swine, and poultry). In 2006, the Canadian dairy herd produced about 7.7 Mt of raw milk, resulting in about 4.4 Mt of dairy products (notably 64% fluid milk and 12% cheese). An integrated cradle-to-gate model (field to processing plant) has been developed to estimate the carbon footprint (CF) of 11 Canadian dairy products. The on-farm part of the model is the Unified Livestock Industry and Crop Emissions Estimation System (ULICEES). It considers all GHG emissions associated with livestock production but, for this study, it was run for the dairy sector specifically. Off-farm GHG emissions were estimated using the Canadian Food Carbon Footprint calculator, (cafoo)(2)-milk. It considers GHG emissions from the farm gate to the exit gate of the processing plants. The CF of the raw milk has been found lower in western provinces [0.93 kg of CO2 equivalents (CO2e)/L of milk] than in eastern provinces (1.12 kg of CO2e/L of milk) because of differences in climate conditions and dairy herd management. Most of the CF estimates of dairy products ranged between 1 and 3 kg of CO2e/kg of product. Three products were, however, significantly higher: cheese (5.3 kg of CO2e/kg), butter (7.3 kg of CO2e/kg), and milk powder (10.1 kg of CO2e/kg). The CF results depend on the milk volume needed, the co-product allocation process (based on milk solids content), and the amount of energy used to manufacture each product. The GHG emissions per kilogram of protein ranged from 13 to 40 kg of CO2e. Two products had higher values: cream and sour cream, at 83 and 78 kg of CO2e/kg, respectively. Finally, the highest CF value was for butter, at about 730 kg of CO2e/kg. This extremely high value is due to the fact that the intensity indicator per kilogram of product is high and that butter is almost exclusively
An environmental impact calculator for greenhouse production systems.
Torrellas, Marta; Antón, Assumpció; Montero, Juan Ignacio
2013-03-30
Multiple web-based calculators have come on the market as tools to support sustainable decision making, but few are available to agriculture. Life cycle assessment (LCA) has proved to be an objective, transparent tool for calculating environmental impacts throughout the life cycle of products and services, but can often be too complex for non-specialists. The objective of this study was therefore to develop an environmental support tool to determine the environmental impacts of protected crops. An effort was made to provide an easy-to-use tool in order to reach a wide audience and help horticulture stakeholders choose efficient options to mitigate the environmental impacts of protected crops. Users can estimate the environmental performance of their crops by entering a limited amount of data and following a few easy steps. A questionnaire must be answered with data on the crop, greenhouse dimensions, substrate, waste management, and the consumption of water, energy, fertilisers and pesticides. The calculator was designed as a simplified LCA, based on two scenarios analysed in detail in previous tasks of the EUPHOROS project and used as reference systems in this study. Two spreadsheets were provided based on these reference scenarios: one for a tomato crop in a multi-tunnel greenhouse under Southern European climate conditions and the other for a tomato crop in a Venlo glass greenhouse under Central European climate conditions. The selected functional unit was one tonne of tomatoes. Default data were given for each reference system for users who did not have complete specific data and to provide results for comparison with users' own results. The results were presented for water use as an inventory indicator and for the impact categories abiotic depletion, acidification, eutrophication, global warming, photochemical oxidation and cumulative energy demand. In the multi-tunnel greenhouse, the main contributors based on the default data were the structure, fertilisers
Numerical Simulation of Shale Gas Production with Thermodynamic Calculations Incorporated
Urozayev, Dias
2015-06-01
In today’s energy sector, it has been observed a revolutionary increase in shale gas recovery induced by reservoir fracking. So-called unconventional reservoirs became profitable after introducing a well stimulation technique. Some of the analysts expect that shale gas is going to expand worldwide energy supply. However, there is still a lack of an efficient as well as accurate modeling techniques, which can provide a good recovery and production estimates. Gas transports in shale reservoir is a complex process, consisting of slippage effect, gas diffusion along the wall, viscous flow due to the pressure gradient. Conventional industrial simulators are unable to model the flow as the flow doesn’t follow Darcy’s formulation. It is significant to build a unified model considering all given mechanisms for shale reservoir production study and analyze the importance of each mechanism in varied conditions. In this work, a unified mathematical model is proposed for shale gas reservoirs. The proposed model was build based on the dual porosity continuum media model; mass conservation equations for both matrix and fracture systems were build using the dusty gas model. In the matrix, gas desorption, Knudsen diffusion and viscous flow were taken into account. The model was also developed by implementing thermodynamic calculations to correct for the gas compressibility, or to obtain accurate treatment of the multicomponent gas. Previously, the model was built on the idealization of the gas, considering every molecule identical without any interaction. Moreover, the compositional variety of shale gas requires to consider impurities in the gas due to very high variety. Peng-Robinson equation of state was used to com- pute and correct for the gas density to pressure relation by solving the cubic equation to improve the model. The results show that considering the compressibility of the gas will noticeably increase gas production under given reservoir conditions and slow down
Ozone production efficiency calculated for different cities in North China
Xue, Min; Ma, Jianzhong
2014-05-01
North China, or Huabei in Chinese, is one of the most severely polluted regions in China. There are many large, complex and strong emission sources in Beijing, Tianjin and Tangshan (together called Jing-Jin-Tang in Chinese) and other urban and industrial centers in Huabei. We applied a regional chemical transport model including the tracer-tagging technique to investigate the chemical characteristics of air masses from different pollution hotspots in Huabei during the IPAC-NC campaign in spring 2006. We calculated the ozone production efficiency of NOx (OPEx) using selected data points of Ox and NOz corresponding to a large number of model grids, which have a good representation of the chemical characteristics of air masses for an entire investigated region. The estimated OPEx for Beijing, Tianjin, Tangshan, and Shijiazhuang general plumes is 3.35, 2.75, 1.43 and 2.33 mole/mole, respectively. We also calculated the OPEx using selected data points of Ox and NOz corresponding to different air masses arriving at Xin'an (one model grid), a rural station located in the center part of Jing-Jin-Tang. The estimated OPEx in Beijing, Tianjin, and Tangshan air masses arriving at Xin'an is 2.98, 2.52, and 1.42 mole/mole, respectively. The difference in estimated OPEx can be attributed to the difference in the emission source types and strength between these regions. The estimated OPEx in Beijing, Tianjin and Tangshan air masses arriving at Xin'an are comparable to those in their general pollution plumes. This indicates that air masses from different urban and industrial centers in Huabei can also maintain their different chemical characteristics while being transported to the rural areas.
Methodology for calculation of carbon balances for biofuel crops production
Gerlfand, I.; Hamilton, S. K.; Snapp, S. S.; Robertson, G. P.
2012-04-01
Understanding the carbon balance implications for different biofuel crop production systems is important for the development of decision making tools and policies. We present here a detailed methodology for assessing carbon balances in agricultural and natural ecosystems. We use 20 years of data from Long-term Ecological Research (LTER) experiments at the Kellogg Biological Station (KBS), combined with models to produce farm level CO2 balances for different management practices. We compared four grain and one forage systems in the U.S. Midwest: corn (Zea mays) - soybean (Glycine max) - wheat (Triticum aestivum) rotations managed with (1) conventional tillage, (2) no till, (3) low chemical input, and (4) biologically-based (organic) practices; and (5) continuous alfalfa (Medicago sativa). In addition we use an abandoned agricultural field (successionnal ecosystem) as reference system. Measurements include fluxes of N2O and CH4, soil organic carbon change, agricultural yields, and agricultural inputs (e.g. fertilization and farm fuel use). In addition to measurements, we model carbon offsets associated with the use of bioenergy from agriculturally produced crops. Our analysis shows the importance of establishing appropriate system boundaries for carbon balance calculations. We explore how different assumptions regarding production methods and emission factors affect overall conclusions on carbon balances of different agricultural systems. Our results show management practices that have major the most important effects on carbon balances. Overall, agricultural management with conventional tillage was found to be a net CO2 source to the atmosphere, while agricultural management under reduced tillage, low input, or organic management sequestered carbon at rates of 93, -23, -51, and -14 g CO2e m-2 yr-1, respectively for conventionally tilled, no-till, low-input, and organically managed ecosystems. Perennial systems (alfalfa and the successionnal fields) showed net carbon
Analyzing the Accuracy of Calculations When Scoping Product Configuration Projects
DEFF Research Database (Denmark)
Bonev, Martin; Hvam, Lars
2012-01-01
Product configurators have increasingly been applied in industrial environments. With their help, companies providing customized products have managed to redesign their specification processes and to better handle the growing product variety. But despite the promising benefits, conducting...
Mohammad Reza Abbasi; Ali Reza Zamanian
2012-01-01
The present paper describes the concept and process of product life cycle in target market of the present commercial organizations. The results of the present study shows that the organization be familiar in target market via knowledge management with the concept and product life cycle of the goods, requires a good planning about the relationship of these two factors. The research population includes electrical and electronically industries of Mazandaran province, Pishraneh Productive-commerc...
Measurement, calculation and evaluation of photon production cross-sections
International Nuclear Information System (INIS)
The meeting proceedings were divided into three sessions devoted to the following topics: Experimental measurement and techniques (3 papers), calculation of photon cross-sections (9 papers), and evaluation (2 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs
Uncertainties in fission-product decay-heat calculations
Energy Technology Data Exchange (ETDEWEB)
Oyamatsu, K.; Ohta, H.; Miyazono, T.; Tasaka, K. [Nagoya Univ. (Japan)
1997-03-01
The present precision of the aggregate decay heat calculations is studied quantitatively for 50 fissioning systems. In this evaluation, nuclear data and their uncertainty data are taken from ENDF/B-VI nuclear data library and those which are not available in this library are supplemented by a theoretical consideration. An approximate method is proposed to simplify the evaluation of the uncertainties in the aggregate decay heat calculations so that we can point out easily nuclei which cause large uncertainties in the calculated decay heat values. In this paper, we attempt to clarify the justification of the approximation which was not very clear at the early stage of the study. We find that the aggregate decay heat uncertainties for minor actinides such as Am and Cm isotopes are 3-5 times as large as those for {sup 235}U and {sup 239}Pu. The recommended values by Atomic Energy Society of Japan (AESJ) were given for 3 major fissioning systems, {sup 235}U(t), {sup 239}Pu(t) and {sup 238}U(f). The present results are consistent with the AESJ values for these systems although the two evaluations used different nuclear data libraries and approximations. Therefore, the present results can also be considered to supplement the uncertainty values for the remaining 17 fissioning systems in JNDC2, which were not treated in the AESJ evaluation. Furthermore, we attempt to list nuclear data which cause large uncertainties in decay heat calculations for the future revision of decay and yield data libraries. (author)
AN ECONOMETRICAL MODEL FOR CALCULATING THE ROMANIAN GROSS DOMESTIC PRODUCT
Ana Maria Mihaela Iordache; Ionela Catalina Tudorache; Mihai Tiberiu Iordache
2011-01-01
This article analyzes the possibility of determining the Romanian Gross Domestic Product on the basis of a linear model, based on macroeconomic indicators such as unemployment, inflation, exchange rate. The proposed solution allows forecasting the Gross Domestic Product for the following period of time based on equation determined from the model in order to develop scenarios for improving the macroeconomic situation of Romania. The article also can be a starting point in the field of strategi...
Two photon production of charm states - a charmonium calculation
International Nuclear Information System (INIS)
The comparison of the nonrelativistic multichannel calculation with the double Rutherford process shows that duality is satisfied, in the sense that if one averages the actual cross sections for a wide enough range of W one gets the same result as for nonstrongly interacting point like quarks. It has been shown for the case of e+e- annihilation that duality in this sense follows from nonrelativistic potential models; and it has been verified that this proof can be extended to two-photon processes
Quark model calculation of charmed baryon production by neutrinos
International Nuclear Information System (INIS)
We study the neutrino production of 25 low-lying charmed baryon resonances in the four flavour quark model. The mass difference of ordinary and charmed quarks is explicitly taken into account. The quark model is used to determine the spectrum of the charmed baryon resonances and the q2 = 0 values of the weak current transition matrix elements. These transition matrix elements are then continued to space-like q2-values by a generalized meson dominance ansatz for a set of suitably chosen invariant form factors. We find that the production of the L = 0 states C0, C1 and C1* is dominant, with the C0 produced most copiously. For L = 1, 2 the Jsup(P) = 3/2- 5/2+ charm states are dominant. We give differential cross sections, total cross sections and energy integrated total cross sections using experimental neutrino fluxes. (orig./BJ)
Model Calculation of Fission Product Yields Data using GEF Code
International Nuclear Information System (INIS)
Fission yields data are classified with spontaneous fission data and neutron induced fission data. The fission product yields data at several energy points for the limited actinides are included in nuclear data libraries such as ENDF/B, JEFF and JENDL because production of those is based mainly on experimental results and it is very difficult to conduct experiments for all actinides and continuous energies. Therefore, in order to obtain fission yields data without experimental data, a theoretical fission model should be introduced to produce the yields data. GEneral Fission model (GEF) is developed to predict the properties for fissioning systems that have not been measured and that are not accessible to experiment. In this study, the fission yields data generated from GEF code are compared with the measured data and the recently available nuclear data libraries. The GEF code is very powerful tool to generate fission yields without measurements. Also, it can produce the distribution of fission product yields for continuous neutron energy while measured data are given only at several energies. The fission yields data of 235U have been tentatively generated with GEF code in this work. Comparing GEF results with measurements and recently released evaluated fission yields data, it is confirmed that GEF code can successfully predict the fission yields data. With its sophisticated model, GEF code is playing a significant role in nuclear industry
Benchmark calculations on residue production within the EURISOL DS project; Part I: thin targets
David, J.C; Boudard, A; Doré, D; Leray, S; Rapp, B; Ridikas, D; Thiollière, N
Report on benchmark calculations on residue production in thin targets. Calculations were performed using MCNPX 2.5.0 coupled to a selection of reaction models. The results were compared to nuclide production cross-sections measured in GSI in inverse kinematics
HEINBE; the calculation program for helium production in beryllium under neutron irradiation
International Nuclear Information System (INIS)
HEINBE is a program on personal computer for calculating helium production in beryllium under neutron irradiation. The program can also calculate the tritium production in beryllium. Considering many nuclear reactions and their multi-step reactions, helium and tritium productions in beryllium materials irradiated at fusion reactor or fission reactor may be calculated with high accuracy. The calculation method, user's manual, calculated examples and comparison with experimental data were described. This report also describes a neutronics simulation method to generate additional data on swelling of beryllium, 3,000-15,000 appm helium range, for end-of-life of the proposed design for fusion blanket of the ITER. The calculation results indicate that helium production for beryllium sample doped lithium by 50 days irradiation in the fission reactor, such as the JMTR, could be achieved to 2,000-8,000 appm. (author)
Improved calculation of total cross section for pair production by relativistic heavy ions
Eby, P. B.
1989-01-01
A calculation of the total cross section for direct electron-positron pair production by heavy ions is described. It combines the use of the Weizsaecker-Williams method for low-energy transfers and existing calculations for high-energy transfers. Higher-order corrections to the total cross section are calculated based on the Weizsaecher-Williams method and existing results for pair production by photons.
FISPRO: a simplified computer program for general fission product formation and decay calculations
International Nuclear Information System (INIS)
This report describes a computer program that solves a general form of the fission product formation and decay equations over given time steps for arbitrary decay chains composed of up to three nuclides. All fission product data and operational history data are input through user-defined input files. The program is very useful in the calculation of fission product activities of specific nuclides for various reactor operational histories and accident consequence calculations
37 CFR 1.779 - Calculation of patent term extension for a veterinary biological product.
2010-07-01
... extension for a veterinary biological product. 1.779 Section 1.779 Patents, Trademarks, and Copyrights... Calculation of patent term extension for a veterinary biological product. (a) If a determination is made pursuant to § 1.750 that a patent for a veterinary biological product is eligible for extension, the...
Calculation of isotopic mass and energy production by a matrix operator method
International Nuclear Information System (INIS)
The Volterra method of the multiplicative integral is used to determine the isotopic density, mass, and energy production in linear systems. The solution method, assumptions, and limitations are discussed. The method allows a rapid accurate calculation of the change in isotopic density, mass, and energy production independent of the magnitude of the time steps, production or decay rates, or flux levels
Energy Technology Data Exchange (ETDEWEB)
Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
2014-10-15
KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist.
International Nuclear Information System (INIS)
KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist
Energy Technology Data Exchange (ETDEWEB)
Bellido, Luis F.
1995-07-01
A computer code to calculate the projectile energy degradation along a target stack was developed for an IBM or compatible personal microcomputer. A comparison of protons and deuterons bombarding uranium and aluminium targets was made. The results showed that the data obtained with TRANGE were in agreement with other computers code such as TRIM, EDP and also using Williamsom and Janni range and stopping power tables. TRANGE can be used for any charged particle ion, for energies between 1 to 100 MeV, in metal foils and solid compounds targets. (author). 8 refs., 2 tabs.
Methods of Cost Accounting and Production Costs Calculation: Merits and Demerits
Alla Pohosova; Olena Yarmolyuk
2012-01-01
The methods of cost accounting and calculation of production costs, including standard-cost, direct-costing, re-distribution and customized ones, their advantages and disadvantages have been analyzed. The proposals on the implementation of methods of cost accounting and production cost calculation in agricultural enterprises have been given. In addition, the application of the combined method of cost accounting of dairy cattle-breeding output has been accentuated
Benchmark calculations on residue production within the EURISOL DS project; Part II: thick targets
David, J.-C; Boudard, A; Doré, D; Leray, S; Rapp, B; Ridikas, D; Thiollière, N
Benchmark calculations on residue production using MCNPX 2.5.0. Calculations were compared to mass-distribution data for 5 different elements measured at ISOLDE, and to specific activities of 28 radionuclides in different places along the thick target measured in Dubna.
Shielding calculation of the radioisotope production channel at 'Tesla' cyclotron installation
International Nuclear Information System (INIS)
During construction of the 'Tesla' Accelerator Installation in the Vinca Institute, one of the important problems was shielding calculation for the Radioisotope production Channel. Calculations were made in three different methods: empirical, semiempirical and Monte Carlo method. The results have been compared and show good agreement. (author)
235U fission product gamma spectra: a comparison between experiment and calculation
International Nuclear Information System (INIS)
Recent measurements of 235U fission product gamma spectra (ORNL), after reduction to a broad group structure, were compared with results of corresponding summation calculations which were made with the UKFPDD-1 fission product data base. In order to facilitate convenient integration of the summation results, weighted sums of decaying exponentials were accurately fitted to them using an iterative least-squares method described. The comparisons between experiment and calculation reveal significant deficiencies in data for short-lived nuclides which prevent the accurate calculation of short-term ( 5 MeV are also examined briefly and possible causes for them are discussed. (author)
Augmentation of ENDF/B fission product gamma-ray spectra by calculated spectra
International Nuclear Information System (INIS)
Gamma-ray spectral data of the ENDF/B-V fission product decay data file have been augmented by calculated spectra. The calculations were performed with a model using beta strength functions and cascade gamma-ray transitions. The calculated spectra were applied to individual fission product nuclides. Comparisons with several hundred measured aggregate gamma spectra after fission were performed to confirm the applicability of the calculated spectra. The augmentation was extended to a preliminary ENDF/B-VI file, and to beta spectra. Appendix C provides information on the total decay energies for individual products and some comparisons of measured and aggregate values based on the preliminary ENDF/B-VI files. 15 refs., 411 figs
Calculation of LUEC using HEEP Software for Nuclear Hydrogen Production Plant
International Nuclear Information System (INIS)
To achieve the hydrogen economy, it is very important to produce a massive amount of hydrogen in a clean, safe and efficient way. Nuclear production of hydrogen would allow massive production of hydrogen at economic prices while avoiding environments pollution by reducing the release of carbon dioxide. A Very High Temperature Reactor (VHTR) is considered as an efficient reactor to couple with the thermo-chemical Sulfur Iodine (SI) cycle to achieve the hydrogen economy. HEEP(Hydrogen Economy Evaluation Program) is one of the software tools developed by IAEA to evaluate the economy of the nuclear hydrogen production system by estimating unit hydrogen production cost. In this paper, the LUHC (Levelized Unit Hydrogen Cost) is calculated by using HEEP for nuclear hydrogen production plant, which consists of 4 modules of 600 MWth VHTR coupled with SI process. The levelized unit hydrogen production cost(LUHC) was calculated by the HEEP software
Calculation of LUEC using HEEP Software for Nuclear Hydrogen Production Plant
Energy Technology Data Exchange (ETDEWEB)
Kim, Jongho; Lee, Kiyoung; Kim, Minhwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
2015-05-15
To achieve the hydrogen economy, it is very important to produce a massive amount of hydrogen in a clean, safe and efficient way. Nuclear production of hydrogen would allow massive production of hydrogen at economic prices while avoiding environments pollution by reducing the release of carbon dioxide. A Very High Temperature Reactor (VHTR) is considered as an efficient reactor to couple with the thermo-chemical Sulfur Iodine (SI) cycle to achieve the hydrogen economy. HEEP(Hydrogen Economy Evaluation Program) is one of the software tools developed by IAEA to evaluate the economy of the nuclear hydrogen production system by estimating unit hydrogen production cost. In this paper, the LUHC (Levelized Unit Hydrogen Cost) is calculated by using HEEP for nuclear hydrogen production plant, which consists of 4 modules of 600 MWth VHTR coupled with SI process. The levelized unit hydrogen production cost(LUHC) was calculated by the HEEP software.
International Nuclear Information System (INIS)
Cross sections for the proton-induced production of radionuclides (40 less than or equal to A less than or equal to 60) from natural titanium, iron, and nickel were measured for proton energies from 80 to 200 MeV. The experimental data were compared with calculations according to Blann's hybrid model of nuclear reactions and to the semiempirical formulas of Rudstam and of Silberberg and Tsao. Based mainly on the new excitation functions, the production rates of cosmogenic radionuclides in meteorites by primary galactic protons were calculated. Since the interaction of primary solar and galactic particles with meteorites can be described with accuracy, the model calculations allow for a quantitative estimate of the action of secondary particles in meteorites. A method of completely describing the production of cosmogenic nuclides in meteorites that takes into account all sources of production is proposed. 51 references
Higher Order QED Calculation of Ultrarelativistic Heavy Ion Production of mu+ mu- Pairs
Baltz, A. J.
2009-01-01
A higher order QED calculation of the ultraperipheral heavy ion cross section for mu+ mu- pair production at RHIC and LHC is carried out. The so-called "Coulomb corrections" lead to an even greater percentage decrease of mu+ mu- production from perturbation theory than the corresponding decrease for e+ e- pair production. Unlike the e+ e- case, the finite charge distribution of the ions (form factor) and the necessary subtraction of impact parameters with matter overlap are significant effect...
Development of a cost calculation model and cost index for sheep production
Directory of Open Access Journals (Sweden)
Camila Raineri
2015-12-01
Full Text Available ABSTRACT The objective of this study was to develop a model for calculation and analysis of production costs of lamb and, from that, to elaborate a production cost index. Panel meetings were held in five regions of the state of São Paulo, Brazil, to define technical features of representative properties of lamb production, taken as a basis for the preparation of the cost calculation model. Then the model for production cost calculation was built. The third step consisted of monitoring prices of inputs used, calculating production costs along the studied period, and generating the cost index, by the Laspeyres model. Lastly, questionnaires were applied to sheep producers, to validate the cost index. The model for production cost calculation was planned to be of easy utilization by farmers, and simultaneously faithful to the theoretical principles. The adopted scheme of cost allocation followed the classification of "variable", "fixed operating", and "income of factors". We generated cost indexes for each of the five studied regions, which were then aggregated in a state index, by weighting regional indexes by flock size. More than 97% of the answers to the validation questionnaires were positive, so we considered that the index reached a high level of approval. The application of Economic Theory is essential for the development of cost calculation models. The developed model has potential to generate important information that can help producers to make decisions. It can work in many contexts, and it can even be adapted to other livestock species. The production cost index for lamb was approved and can collaborate with the organization of the sheep agroindustrial system.
Cristiana Bogdanoiu
2011-01-01
The development of food industry of manufacturing dairy products in our country imposes increased efforts to find the most judicious means for management accounting and cost calculation improvement, in order to thoroughly identify and mobilize the existing internal reserves to achieve economic growth. The management accounting and costs calculation improvement, as a basic element of the accounting system, without which an efficient leadership of internal management activities can not be achie...
Calculated leaching of certain fission products from a cylinder of French glass
International Nuclear Information System (INIS)
The probable total leaching of the most important fission products and actinides have been tabulated for a cylinder of French HLW glass with approximately 9 percent fission products. The calculations cover the period between 30 and 10000 years after removal from the reactor. The cylinder is of the type planned for the introduction of the HLW into Swedish crystalline rocks. All the components are supposed to have the same leach rate. The calculations also include the probable thickness of eroded glass layer/year. (author)
Calculation of Complexity Costs – An Approach for Rationalizing a Product Program
DEFF Research Database (Denmark)
Hansen, Christian Lindschou; Mortensen, Niels Henrik; Hvam, Lars
2012-01-01
of suggested Life Cycle Complexity Factors (LCCFs). The suggested method has been tested in an action based research study with promising results. The case study shows how the allocation of complexity costs on individual product variants provides previously unknown insights into the true cost structure......This paper proposes an operational method for rationalizing a product program based on the calculation of complexity costs. The method takes its starting point in the calculation of complexity costs on a product program level. This is done throughout the value chain ranging from component...... inventories at the factory sites, all the way to the distribution of finished goods from distribution centers to the customers. The method proposes a step-wise approach including the analysis, quantification and allocation of product program complexity costs by the means of identifying of a number...
Fission Product Decay Heat Calculations for Neutron Fission of 232Th
Son, P. N.; Hai, N. X.
2016-06-01
Precise information on the decay heat from fission products following times after a fission reaction is necessary for safety designs and operations of nuclear-power reactors, fuel storage, transport flasks, and for spent fuel management and processing. In this study, the timing distributions of fission products' concentrations and their integrated decay heat as function of time following a fast neutron fission reaction of 232Th were exactly calculated by the numerical method with using the DHP code.
Preliminary Calculation of the EROI for the Production of Crude Oil and Light Oil Products in Russia
Directory of Open Access Journals (Sweden)
Alexander Safronov
2014-09-01
Full Text Available Russia is one of the world’s largest producers of energy resources. The production of energy resources in Russia is profitable both economically and in terms of energy production. Currently, Russian oil and gas companies have a policy of increasing energy efficiency, which will led to an increase in the energy return on investment (EROI of both oil and gas production as a whole, and of separate companies in particular. By our calculations, the EROI for oil production in Russia differs for the different companies, and in 2012 was in the range of 22–35:1. The EROI for light oil products in 2012 was in the range of 5–13:1.
International Nuclear Information System (INIS)
The alternatives for calculation of energy marginal cost in hydroelectric systems, considering the transmission one, was analysed, including fundamental concepts; generation/transmission systems, represented by linear power flow model; production marginal costs in hydrothermal systems and computation aspects. (C.G.C.). 11 refs, 5 figs
Heat production in growing pigs calculated according to the RQ and CN methods
DEFF Research Database (Denmark)
Christensen, K; Chwalibog, André; Henckel, S;
1988-01-01
1. Heat production, calculated according to the respiratory quotient methods, HE(RQ), and the carbon nitrogen balance method, HE(CN), was compared using the results from a total of 326 balance trials with 56 castrated male pigs fed different dietary composition and variable feed levels during the...
International Nuclear Information System (INIS)
The report summarizes results of the Coordinated Research Project (CRP) devoted to photon preduction in neutron-induced reactions. The report presents 25 original contributions that reflect accomplishments achieved in measurement, calculation and evaluation of photon production under the project in 1994-1997. Major results are highlighted and a list of the CRP publications is given. (author)
Directory of Open Access Journals (Sweden)
Baranovskaya T. P.
2014-06-01
Full Text Available The article describes the fuzzy-multiple approach and the block of fuzzy (interval mathematical models developed by the authors for calculating the amounts of material and financial flows, prices for bread and economic efficiency in a technologically integrated bread production system
COMPLEX INNER PRODUCT AVERAGING METHOD FOR CALCULATING NORMAL FORM OF ODE
Institute of Scientific and Technical Information of China (English)
陈予恕; 孙洪军
2001-01-01
This paper puts forward a complex inner product averaging method for calculating normal form of ODE. Compared with conventional averaging method, the theoretic analytical process has such simple forms as to realize computer program easily.Results can be applied in both autonomous and non-autonomous systems. At last, an example is resolved to verify the method.
Calculation of fissile nuclides and fission products inventory applied to ETRR-1 research reactor
International Nuclear Information System (INIS)
The study of the nuclear reactor fuel safety implies studying physical mechanical, thermal and chemical proportions of the fuel during normal operation and accident conditions. A model was developed to calculate the fissile nuclides and fission products inventory in an operating reactor. The model considers the production and removal of different radionuclides leaking into account the decay schemes of each. The mathematical formulas were treated without any approximations. A decay model was developed for the period after reactor shutdown. The amount of different nuclides was evaluated for a given cooling time. Egypt test and research reactor number 1, ETRR-1. Was chosen to apply the model. The amount of about 200 nuclides was calculated. A certain nuclides was chosen to be presented based on their poisoning ratios. Criticality calculations were carried out to investigate the criticality condition of the reactor at different operating times. 4 fig
FOOD: an interactive code to calculate internal radiation doses from contaminated food products
International Nuclear Information System (INIS)
An interactive code, FOOD, has been written in BASIC for the UNIVAC 1108 to facilitate calculation of internal radiation doses to man from radionuclides in food products. In the dose model, vegetation may be contaminated by either air or irrigation water containing radionuclides. The model considers two mechanisms for radionuclide contamination of vegetation: direct deposition on leaves and uptake from soil through the root system. The user may select up to 14 food categories with corresponding consumption rates, growing periods and either irrigation rates or atmospheric deposition rates. These foods include various kinds of produce, grains and animal products. At present, doses may be calculated for the skin, total body and five internal organs from 190 radionuclides. Dose summaries can be displayed at the local terminal. Further details on percent contribution to dose by nuclide and by food type are available from an auxiliary high-speed printer. This output also includes estimated radionuclide concentrations in soil, plants and animal products
Calculation Model of Safety Level of Production Logistics System in Coal Mine
Directory of Open Access Journals (Sweden)
Zhai Xue-Qi
2013-01-01
Full Text Available Many factors affecting the safety of production logistics system of coal mine and the impact of these factors on the safety degree is not consistent, this study determines the safety indicators from five aspects, such as, the personal quality, mechanical equipment, environment, safety management and emergency rescue, etc. This study fitted the interaction of safety indicator and safety level by using the polynomial model and constructing security level calculation model through the analysis of regression model and its coefficient. This article proposes a method of calculating the safety production level of coal mine by using polynomial model, this method helps to indicate direction for analyzing safety production status and raising safety level of coal mining enterprise.
Odland, D; Davis, C
1982-08-01
Plain muffins, yellow cake, baked custard, apple pie, tuna casserole, frozen tuna casserole, cheese soufflé, and meat loaf were baked in preheated and non-preheated standard gas, continuous-clean gas, standard electric, and self-cleaning electric ovens. Products generally required 5 min. or less extra baking time when cooked in non-preheated rather than in preheated ovens. The variability in baking times often was less between preheated and non-preheated ovens than among oven types. Calculated energy consumption values showed that usually less energy was required to bake products in non-preheated than in preheated ovens; savings averaged about 10 percent. Few significant differences were found in physical measurements or eating quality either between preheated and non-preheated ovens or among oven types. Overall, for the products tested, findings confirmed that preheating the oven is not essential for good product quality and, therefore, is an unnecessary use of energy. PMID:7108076
Evaluation of fission product worth margins in PWR spent nuclear fuel burnup credit calculations
International Nuclear Information System (INIS)
Current criticality safety calculations for the transportation of irradiated LWR fuel make the very conservative assumption that the fuel is fresh. This results in a very substantial overprediction of the actual keff of the transportation casks; in certain cases, this decreases the amount of spent fuel which can be loaded in a cask, and increases the cost of transporting the spent fuel to the repository. Accounting for the change of reactivity due to fuel depletion is usually referred to as ''burnup credit.'' The US DOE is currently funding a program aimed at establishing an actinide only burnup credit methodology (in this case, the calculated reactivity takes into account the buildup or depletion of a limited number of actinides). This work is undergoing NRC review. While this methodology is being validated on a significant experimental basis, it implicitly relies on additional margins: in particular, the absorption of neutrons by certain actinides and by all fission products is not taken into account. This provides an important additional margin and helps guarantee that the methodology is conservative provided these neglected absorption are known with reasonable accuracy. This report establishes the accuracy of fission product absorption rate calculations: (1) the analysis of European fission product worth experiments demonstrates that fission product cross-sections available in the US provide very good predictions of fission product worth; (2) this is confirmed by a direct comparison of European and US cross section evaluations; (3) accuracy of Spent Nuclear Fuel (SNF) fission product content predictions is established in a recent ORNL report where several SNF isotopic assays are analyzed; and (4) these data are then combined to establish in a conservative manner the fraction of the predicted total fission product absorption which can be guaranteed based on available experimental data
Classification and calculation of primary failure modes in bread production line
International Nuclear Information System (INIS)
In this study, we describe the classification methodology over a 2-year period of the primary failure modes in categories based on failure data of bread production line. We estimate the probabilities of these categories applying the chi-square goodness of fit test, and we calculate their joint probabilities of mass function at workstation and line level. Then, we present numerical examples in order to predict the causes and frequencies of breakdowns for workstations and for the entire bread production line that will occur in the future. The methodology is meant to guide bread and bakery product manufacturers, improving the operation of the production lines. It can also be a useful tool to maintenance engineers, who wish to analyze and improve the reliability and efficiency of the manufacturing systems
Methodology for fission product release calculations during an ACR-1000 end-fitting failure event
International Nuclear Information System (INIS)
The ACR-1000® reactor enhances and retains the proven features of the CANDU® design such as the concept of the horizontal fuel channel core. At each end of a fuel channel, there is an end-fitting incorporating a feeder connection through which pressurized coolant enters and leaves the fuel channel, where 12 fuel bundles are inserted. The safety analysis cases include postulated end-fitting failure events to assess the fission product releases from all fuel bundles which would be ejected out of the channel and oxidized in the air-steam environment under decay power. This paper presents the methodology used in assessing the fuel behaviour and the fission product releases during a postulated end-fitting failure in an ACR-1000 reactor. After the end-fitting failure, the 12 fuel bundles are ejected out of the channel and drop onto the fuelling machine vault floor. The fuel bundles are likely heavily damaged by impact and would break into small clusters of elements or fragments. To calculate the fission product releases from an individual fragment, the transient fuel temperature is numerically solved by differential heat equations; the air oxidation model is chosen for the event accordingly; and the fission product inventory and releases are estimated by computer codes ORIGEN-S, CATHENA, ELESTRES and SOURCE-IST. Finally, the total fission product releases from all fragments into containment are calculated. This methodology has been developed for ACR-1000 safety analysis, which is also applicable to CANDU. With the new methodology, the transient releases from up to 150 fission products can be estimated as detail as in fragment. In this paper, a sample calculation is also provided to show the application of the methodology in ACR-1000 safety analysis for end-fitting failure. (author)
Development of calculation code of fission products specific activity in primary coolant
International Nuclear Information System (INIS)
Based on an assumption of that there is a design basis fuel defect level from reactor startup, calculation method of fission products specific activities in primary coolant is studied. Time-dependent nuclide activities in defect fuel are calculated by ORIGEN code, and nuclide releases from the defect fuel are considered. After processed by interface codes, data are used by PCFPA code which is used to calculate nuclide activities in the coolant. PCFPA solves differential equations by unit of decay chain, and totally considers decay's contribution to nuclide activities, and considers different system design between secondary and third generation plants such as AP1000. The method could provide the maximum of specific activity during plant operation and their results are consistent with data in AP1000 DCD(Rev.16). The method could be applicable to shielding design in secondary and third generation plants such as AP1000. (authors)
Application of Origen2.1 in the decay photon spectrum calculation of spallation products
Hong, Shuang; Xu, Hu-Shan; Meng, Hai-Yan; Zhang, Lu; Liu, Zhao-Qing; Gao, Yu-Cui; Chen, Kang
2016-01-01
Origen2.1 is a widely used computer code for calculating the burnup, decay, and processing of radioactive materials. However, the nuclide library of Origen2.1 is used for existing reactors like pressurized water reactor, to calculate the photon spectrum released by the decay of spallation products, we have made specific libraries for the ADS tungsten spallation target, based on the results given by a Monte Carlo code: FLUKA. All the data used to make the Origen2.1 libraries is obtained from Nuclear structure & decay Data (NuDat2.6). The accumulated activity of spallation products and the contribution of nuclides to photon emission are given in this paper.
Fission product inventory calculation by a CASMO/ORIGEN coupling program
International Nuclear Information System (INIS)
A CASMO/ORIGEN coupling utility program was developed to predict the composition of all the fission products in spent PWR fuels. The coupling program reads the CASMO output file, modifies the ORIGEN cross section library and reconstructs the ORIGEN input file at each depletion step. In ORIGEN, the burnup equation is solved for actinides and fission products based on the fission reaction rates and depletion flux of CASMO. A sample calculation has been performed using a 14 x 14 PWR fuel assembly and the results are given in this paper
Fission product inventory calculation by a CASMO/ORIGEN coupling program
Energy Technology Data Exchange (ETDEWEB)
Kim, Do Heon; Kim, Jong Kyung [Hanyang University, Seoul (Korea, Republic of); Choi, Hang Bok; Roh, Gyu Hong; Jung, In Ha [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
1997-12-31
A CASMO/ORIGEN coupling utility program was developed to predict the composition of all the fission products in spent PWR fuels. The coupling program reads the CASMO output file, modifies the ORIGEN cross section library and reconstructs the ORIGEN input file at each depletion step. In ORIGEN, the burnup equation is solved for actinides and fission products based on the fission reaction rates and depletion flux of CASMO. A sample calculation has been performed using a 14 x 14 PWR fuel assembly and the results are given in this paper. 3 refs., 1 fig., 1 tab. (Author)
Method of calculation of tanks forced ventilation from the remnants of liquid products
Directory of Open Access Journals (Sweden)
С. О. Пузік
2013-07-01
Full Text Available The advantages of gasoline compared to other petroleum products in terms of feasibility of their research. Calculations of the duration of ventilation and changes in the concentration of vapors of gasoline remains in the gas space of the vertical tank with a capacity of 1000 m3 (RUS-1000. Nomogram constructed for the quantitative forecast available liquid balances petrol A-95 and the time duration ventylyaiyi RUS-1000 from the remnants of the petrol
Nuclear data production, calculation and measurement: a global overview of the gamma heating issue
Gueton O.; Régnier D.; Ravaux S.; Fourmentel D.; Amharrak H.; Colombier A-C.; Hudelot J-P.; Lemaire M.
2013-01-01
The gamma heating evaluation in different materials found in current and future generations of nuclear reactor (EPRTM, GENIV, MTR-JHR), is becoming an important issue especially for the design of many devices (control rod, heavy reflector, in-core & out-core experiments…). This paper deals with the works started since 2009 in the Reactor Studies Department of CEA Cadarache in ordre to answer to several problematic which have been identified as well for nuclear data production and calculation ...
Calculation of heavy ion e+ e- pair production to all orders in Z alpha
Baltz, Anthony J.
2004-01-01
The heavy ion total cross section for continuum e+ e- pair production has been calculated to all orders in Z alpha. The formula resulting from an exact solution of the semiclassical Dirac equation in the ultrarelativistic limit is evaluated numerically. An energy dependent spatial cutoff of the heavy ion potential is utilized, leading to an exact formula agreeing with the known perturbative formula in the ultrarelativistic, perturbative limit. Cross sections and sample momentum distributions ...
Luef, Birgit; Luef, Franz; Peduzzi, Peter
2009-01-01
Assessing viral production (VP) requires robust methodological settings combined with precise mathematical calculations. This contribution improves and standardizes mathematical calculations of VP and the assessment of the proportion of lysogenic cells in a sample. We present an online tool ‘Viral Production Calculator’ (vipcal, http://www.univie.ac.at/nuhag-php/vipcal) that calculates lytic production and the percentage of lysogenic cells based on data obtained from a viral reduction approac...
Barber, Duncan Henry
During some postulated accidents at nuclear power stations, fuel cooling may be impaired. In such cases, the fuel heats up and the subsequent increased fission-gas release from the fuel to the gap may result in fuel sheath failure. After fuel sheath failure, the barrier between the coolant and the fuel pellets is lost or impaired, gases and vapours from the fuel-to-sheath gap and other open voids in the fuel pellets can be vented. Gases and steam from the coolant can enter the broken fuel sheath and interact with the fuel pellet surfaces and the fission-product inclusion on the fuel surface (including material at the surface of the fuel matrix). The chemistry of this interaction is an important mechanism to model in order to assess fission-product releases from fuel. Starting in 1995, the computer program SOURCE 2.0 was developed by the Canadian nuclear industry to model fission-product release from fuel during such accidents. SOURCE 2.0 has employed an early thermochemical model of irradiated uranium dioxide fuel developed at the Royal Military College of Canada. To overcome the limitations of computers of that time, the implementation of the RMC model employed lookup tables to pre-calculated equilibrium conditions. In the intervening years, the RMC model has been improved, the power of computers has increased significantly, and thermodynamic subroutine libraries have become available. This thesis is the result of extensive work based on these three factors. A prototype computer program (referred to as SC11) has been developed that uses a thermodynamic subroutine library to calculate thermodynamic equilibria using Gibbs energy minimization. The Gibbs energy minimization requires the system temperature (T) and pressure (P), and the inventory of chemical elements (n) in the system. In order to calculate the inventory of chemical elements in the fuel, the list of nuclides and nuclear isomers modelled in SC11 had to be expanded from the list used by SOURCE 2.0. A
Energy Technology Data Exchange (ETDEWEB)
Smith, P.D.
1978-02-01
A special purpose computer program, TRAFIC, is presented for calculating the release of metallic fission products from an HTGR core. The program is based upon Fick's law of diffusion for radioactive species. One-dimensional transient diffusion calculations are performed for the coated fuel particles and for the structural graphite web. A quasi steady-state calculation is performed for the fuel rod matrix material. The model accounts for nonlinear adsorption behavior in the fuel rod gap and on the coolant hole boundary. The TRAFIC program is designed to operate in a core survey mode; that is, it performs many repetitive calculations for a large number of spatial locations in the core. This is necessary in order to obtain an accurate volume integrated release. For this reason the program has been designed with calculational efficiency as one of its main objectives. A highly efficient numerical method is used in the solution. The method makes use of the Duhamel superposition principle to eliminate interior spatial solutions from consideration. Linear response functions relating the concentrations and mass fluxes on the boundaries of a homogeneous region are derived. Multiple regions are numerically coupled through interface conditions. Algebraic elimination is used to reduce the equations as far as possible. The problem reduces to two nonlinear equations in two unknowns, which are solved using a Newton Raphson technique.
New Calculation of Antiproton Production by Cosmic Ray Protons and Nuclei
Kachelriess, Michael; Moskalenko, Igor V.; Ostapchenko, Sergey S.
2015-04-01
A dramatic increase in the accuracy and statistics of space-borne cosmic ray (CR) measurements has yielded several breakthroughs over the last several years. The most puzzling is the rise in the positron fraction above ∼10 GeV over the predictions of the propagation models assuming pure secondary production. The accuracy of the antiproton production cross section is critical for astrophysical applications and searches for new physics since antiprotons in CRs seem to hold the keys to many puzzles including the origin of those excess positrons. However, model calculations of antiproton production in CR interactions with interstellar gas are often employing parameterizations that are out of date or are using outdated physical concepts. This may lead to an incorrect interpretation of antiproton data which could have broad consequences for other areas of astrophysics. In this work, we calculate antiproton production in pp-, pA-, and AA-interactions using EPOS-LHC and QGSJET-II-04, two of the most advanced Monte Carlo (MC) generators tuned to numerous accelerator data including those from the Large Hadron Collider (LHC). We show that the antiproton yields obtained with these MC generators differ by up to an order of magnitude from yields of parameterizations commonly used in astrophysics.
Preliminary Calculation of the EROI for the Production of Gas in Russia
Directory of Open Access Journals (Sweden)
Roman Nogovitsyn
2014-09-01
Full Text Available Russia is one of the world’s largest producers of energy resources. Production of energy resources in Russia is profitable, both economically and in terms of the energy produced (as measured by EROI. At the present time, Russian oil and gas companies have a policy of energy saving, and data on energy consumption is given in annual reports. Based on these data, we can make the EROI calculation. In 2013, the EROI for the production, transportation and processing of gas for Open joint stock company (OJSC “Gazprom” was 79:1; for OJSC “NOVATEK”, 76:1; for OJSC “Yakutsk Fuel and Energy Company (YATEC”, only for production, 116:1. Currently, the situation in the oil and gas industry has come to a point when there is a need for the introduction of an energy audit.
Nuclear data production, calculation and measurement: a global overview of the gamma heating issue
Colombier, A.-C.; Amharrak, H.; Fourmentel, D.; Ravaux, S.; Régnier, D.; Gueton, O.; Hudelot, J.-P.; Lemaire, M.
2013-03-01
The gamma heating evaluation in different materials found in current and future generations of nuclear reactor (EPRTM, GENIV, MTR-JHR), is becoming an important issue especially for the design of many devices (control rod, heavy reflector, in-core & out-core experiments…). This paper deals with the works started since 2009 in the Reactor Studies Department of CEA Cadarache in ordre to answer to several problematic which have been identified as well for nuclear data production and calculation as for experimental measurement methods. The selected subjects are: Development of a Monte Carlo code (FIFRELIN) to simulate the prompt fission gamma emission which represents the major part of the gamma heating production inside the core Production and qualification of new evaluations of nuclear data especially for radiative capture and inelastic neutron scattering which are the main sources of gamma heating out-core Development and qualification of a recommended method for the total gamma heating calculation using the Monte Carlo simulation code TRIPOLI-4 Development, test and qualification of new devices dedicated to the in-core gamma heating measurement as well in MTR-JHR as in zero power facilities (EOLE-MINERVE) of CEA, Cadarache to increase the experimental measurement accuracy.
In-core thermal hydraulic and fission product calculations for severe fuel damage analyses
International Nuclear Information System (INIS)
Best-estimate calculations of realistic source terms are presented which reduce uncertainties in predicting fission product release from the UO2 fuel over the temperature range between 770 K and 3000 K. The proposed method of correlation includes such fuel morphology effects as equiaxed fuel grain growth and fuel-cladding interaction. The method correlates the product of fuel release rate and equiaxed grain size with the inverse fuel temperature to yield a bulk mass transfer correlation. It was found that less and slower releases are predicted utilizing the bulk mass transfer correlation than such conventional literature correlations as the steam oxidation model and the NUREG-0956 correlation. A Severe Fuel Damage (SFD) analysis code was developed to perform the thermal hydraulic and fission product calculations needed to analyze the Power Burst Facility SFD tests. The predictions utilizing the bulk mass transfer correlations overall followed the experimental time-release histories during the course of the heatup, power hold and cooldown phases of the transients. Good agreements were achieved for the integral releases both in timing and in magnitude. The proposed bulk mass transfer correlations can be applied to both current and advanced light water reactor fuels. 17 refs., 8 figs., 3 tabs
Nuclear data production, calculation and measurement: a global overview of the gamma heating issue
International Nuclear Information System (INIS)
The gamma heating evaluation in different materials found in current and future generations of nuclear reactor (EPR, GEN-IV, MTR-JHR), is becoming an important issue especially for the design of many devices (control rod, heavy reflector, in-core and out-core experiments...). This paper deals with the works started in 2009 in the Reactor Studies Department of CEA Cadarache in order to answer to several issues which have been identified for nuclear data production and calculation and for experimental measurement methods. The selected subjects are: -) The development of a Monte Carlo code (FIFRELIN) to simulate the prompt fission gamma emission which represents the major part of the gamma heating production inside the core; -) The production and qualification of new evaluations of nuclear data especially for radiative capture and inelastic neutron scattering which are the main sources of gamma heating out-core; -) The development and qualification of a recommended method for the total gamma heating calculation using the Monte Carlo simulation code TRIPOLI-4; and -) The development, test and qualification of new devices dedicated to the in-core gamma heating measurement as well in MTR-JHR as in zero power facilities (EOLE-MINERVE) of CEA, Cadarache in order to increase the experimental measurement accuracy. (authors)
Measured and calculated fission-product poisoning in neutron-irradiated uranium-233
International Nuclear Information System (INIS)
Samples of 233U and of natural thorium have been irradiated in high neutron-flux facilities, in both soft and hard neutron spectra, and for both short and long exposure times. Included are exposures resulting in depletions of more than 90 percent of the 233U in the fissile material and burnups of more than 30,000 MWd/MT in the fertile material. Fission-product poison cross sections in two energy groups (thermal and epithermal) exhibit differences between measurement and calculation that are believed to be attributable to a lack of adequate information on important fission products in the literature. Experimental results for transient absorbers in irradiated 233U give at least 20,000 b for the neutron absorption resonance integral of 149Pm. This is a factor of 15 higher than that obtained by a 1/v extrapolation of the thermal cross sections. For transient 135Xe, the measured absorption is 7.5 percent higher than that calculated using ENDF/B-IV data. Information is also provided concerning such matters as fission yields and neutron absorption of neodymium isotopes, the existence of significant transient fission-product poisons other than 135Xe and 149Sm, and the shielding of 233U by 232Th. Such shielding suggests the need for a change in the energy dependence of the 232Th thermal-neutron cross section
Nuclear data production, calculation and measurement: a global overview of the gamma heating issue
Directory of Open Access Journals (Sweden)
Gueton O.
2013-03-01
Full Text Available The gamma heating evaluation in different materials found in current and future generations of nuclear reactor (EPRTM, GENIV, MTR-JHR, is becoming an important issue especially for the design of many devices (control rod, heavy reflector, in-core & out-core experiments…. This paper deals with the works started since 2009 in the Reactor Studies Department of CEA Cadarache in ordre to answer to several problematic which have been identified as well for nuclear data production and calculation as for experimental measurement methods. The selected subjects are: Development of a Monte Carlo code (FIFRELIN to simulate the prompt fission gamma emission which represents the major part of the gamma heating production inside the core Production and qualification of new evaluations of nuclear data especially for radiative capture and inelastic neutron scattering which are the main sources of gamma heating out-core Development and qualification of a recommended method for the total gamma heating calculation using the Monte Carlo simulation code TRIPOLI-4 Development, test and qualification of new devices dedicated to the in-core gamma heating measurement as well in MTR-JHR as in zero power facilities (EOLE-MINERVE of CEA, Cadarache to increase the experimental measurement accuracy.
Mezbahul-Islam, Mohammad; Belanger, Frederic; Chartrand, Patrice; Jung, In-Ho; Coursol, Pascal
2016-04-01
The present work has been performed with the aim to optimize the existing process for the production of high purity bismuth (99.999 pct). A thermo-chemical database including most of the probable impurities of bismuth (Bi-X, X = Ag, Au, Al, Ca, Cu, Fe, Mg, Mn, Na, Ni, Pb, S, Sb, Sn, Si, Te, Zn) has been constructed to perform different thermodynamic calculations required for the refining process. Thermodynamic description for eight of the selected binaries, Bi-Ca, Cu, Mn, Ni, Pb, S, Sb, and Sn, has been given in the current paper. Using the current database, different thermodynamic calculations have been performed to explain the steps involved in the bismuth refining process.
Contribution to decay heat calculation: fission product mean beta and gamma assessment
International Nuclear Information System (INIS)
Following a reactor shutdown, after the fission chain process has completely faded out, a significant quantity of energy (around seven per cent of the total power of the reactor) continues to be generated in the core. This is known as residual power or decay heat. The principal source of this energy is due to the radioactive decay of fission products and is at any time equal to the sum of the powers released by these different nuclei (P = Σ = Pi). Each of the powers Pi is the product of three terms: the concentration of the relevant nuclide, its decay constant and its mean decay energy. The evaluation of the first two term is straightforward. On the other hand the evaluation of the mean energies presents some difficulties due to a lack of data in beta and gamma spectra of some fission products. This study intends, after a critical analysis of the current method of evaluation of the mean energies, to propose a new model for this calculation. The new model tested on several well known nuclides, has been proved correct and precise. It has then been applied to approximatively sixty nuclides among the lesser known ones. The results obtained have lead to a better prediction of both beta and gamma ray components of the residual power. Consequently, this new model, which allows to take into account the lack of beta branching ratio corresponding to the highest levels of the product nucleus in the beta decay reaction, can be adopted to replace the current method, for calculation of the mean energies of fission products, especially in the case of the lesser known nuclides
Energy Technology Data Exchange (ETDEWEB)
Dunn, Jennifer B. [Argonne National Lab. (ANL), Argonne, IL (United States); Qin, Zhangcai [Argonne National Lab. (ANL), Argonne, IL (United States); Mueller, Steffen [Univ. of Illinois at Chicago, Chicago, IL (United States); Kwon, Ho-young [International Food Policy Research Institute (IFPRI), Washington, DC (United States); Wander, Michelle M. [Univ. of Illinois, Urbana-Champaign, IL (United States); Wang, Michael [Argonne National Lab. (ANL), Argonne, IL (United States)
2014-09-01
The Carbon Calculator for Land Use Change from Biofuels Production (CCLUB) calculates carbon emissions from land use change (LUC) for four different ethanol production pathways including corn grain ethanol and cellulosic ethanol from corn stover, Miscanthus, and switchgrass. This document discusses the version of CCLUB released September 30, 2014 which includes corn and three cellulosic feedstocks: corn stover, Miscanthus, and switchgrass.
Nuclear model calculation and targetry recipe for production of 110mIn.
Kakavand, T; Mirzaii, M; Eslami, M; Karimi, A
2015-10-01
(110m)In is potentially an important positron emitting that can be used in positron emission tomography. In this work, the excitation functions and production yields of (110)Cd(d, 2n), (111)Cd(d, 3n), (nat)Cd(d, xn), (110)Cd(p, n), (111)Cd(p, 2n), (112)Cd(p, 3n) and (nat)Cd(p, xn) reactions to produce the (110m)In were calculated using nuclear model code TALYS and compared with the experimental data. The yield of isomeric state production of (110)In was also compared with ground state production ones to reach the optimal energy range of projectile for the high yield production of metastable state. The results indicate that the (110)Cd(p, n)(110m)In is a high yield reaction with an isomeric ratio (σ(m)/σ(g)) of about 35 within the optimal incident energy range of 15-5 MeV. To make the target, cadmium was electroplated on a copper substrate in varying electroplating conditions such as PH, DC current density, temperature and time. A set of cold tests were also performed on the final sample under several thermal shocks to verify target resistance. The best electroplated cadmium target was irradiated with 15 MeV protons at current of 100 µA for one hour and the production yield of (110m)In and other byproducts were measured. PMID:26141297
Beam line shielding calculations for an Electron Accelerator Mo-99 production facility
Energy Technology Data Exchange (ETDEWEB)
Mocko, Michal [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
2016-05-03
The purpose of this study is to evaluate the photon and neutron fields in and around the latest beam line design for the Mo-99 production facility. The radiation dose to the beam line components (quadrupoles, dipoles, beam stops and the linear accelerator) are calculated in the present report. The beam line design assumes placement of two cameras: infra red (IR) and optical transition radiation (OTR) for continuous monitoring of the beam spot on target during irradiation. The cameras will be placed off the beam axis offset in vertical direction. We explored typical shielding arrangements for the cameras and report the resulting neutron and photon dose fields.
Wouters, Sebastian; Limacher, Peter A; Van Neck, Dimitri; Ayers, Paul W
2012-04-01
We have implemented the sweep algorithm for the variational optimization of SU(2) U(1) (spin and particle number) invariant matrix product states (MPS) for general spin and particle number invariant fermionic Hamiltonians. This class includes non-relativistic quantum chemical systems within the Born-Oppenheimer approximation. High-accuracy ab initio finite field results of the longitudinal static polarizabilities and second hyperpolarizabilities of one-dimensional hydrogen chains are presented. This allows to assess the performance of other quantum chemical methods. For small basis sets, MPS calculations in the saturation regime of the optical response properties can be performed. These results are extrapolated to the thermodynamic limit. PMID:22482543
International Nuclear Information System (INIS)
The decay products of 232U produced in the thorium-uranium fuel cycle emit high energy γ-rays. This affects the fuel cycle greatly. In this paper, the 232U productions in thermal reactor using thorium fuel are analyzed by ORIGEN2, SCALE5 and the code based on the Bateman method. Under normal situation, 232U is mainly produced by 232Th (n, 2n) reaction chain, and more quantity of 230Th can be transformed into 232U while the neutron spectrum is softer. The burnup calculation of CANDU reactor and PWR assembly indicates that the 232U in uranium increase with the burnup, and 230Th in fresh thorium has linear correlation with 232U/Utotal or 232U/233U at discharge burnup. (authors)
Cross sections for fuel depletion and radioisotope production calculations in TRIGA reactors
International Nuclear Information System (INIS)
For TRIGA Reactors, the fuel depletion and isotopic inventory calculations, depends on the computer code and in the cross sections of some important actinides used. Among these we have U-235, U-238, Pu-239, Pu-240 and Pu-241. We choose ORIGEN2, a code with a good reputation in this kind of calculations, we observed the cross sections for these actinides in the libraries that we have (PWR's and BWR), the fission cross section for U-235 was about 50 barns. We used a PWR library and our results were not satisfactory, specially for standard elements. We decided to calculate cross sections more suitable for our reactor, for that purpose we simulate the standard and FLIP TRIGA cells with the transport code WIMS. We used the fuel average flux and COLAPS (a home made program), to generate suitable cross sections for ORIGEN2, by collapsing the WIMS library cross sections of these nuclides. For the radioisotope production studies using the Central Thimble, we simulate the A and B rings and used the A average flux to collapse cross sections. For these studies, the required nuclides sometimes are not present in WIMS library, for them we are planning to process the ENDF/B data, with NJOY system, and include the cross sections to WIMS library or to collapse them using the appropriate average-flux and the program COLAPS. (author)
Benchmark calculations on residue production within the EURISOL DS project. Part 1: thin targets
International Nuclear Information System (INIS)
We have begun this benchmark study using mass distribution data of reaction products obtained at GSI in inverse kinematics. This step has allowed us to make a first selection among 10 spallation models; in this way the first assessment of the quality of the models was obtained. Then, in a second part, experimental mass distributions for some elements, which either are interesting as radioactive ion beams or important due to the safety and radioprotection issues (alpha or gamma emitters), will be also compared to model calculations. These data have been obtained for an equivalent 0.8 or 1.0 GeV proton beam, which is approximately the proposed projectile energy. We note that in realistic thick targets the proton beam will be slowed down and some secondary particles will be produced. Therefore, the residual nuclei production at lower energies is also important. For this reason, we also performed in the third part of this work some excitation function calculations and the associated data obtained with gamma-spectroscopy to test the models in a wide projectile energy range. We conclude that INCL4/Abla and Isabel/Abla are the best model combinations which we recommend. We also note that the agreement between model and data are better with 1 GeV protons than with 100-200 MeV protons
Energy Technology Data Exchange (ETDEWEB)
Honea, R.B.; Petrich, C.H.; Wilson, D.L.; Dillard, C.A.; Durfee, R.C.; Faber, J.A.
1979-04-01
This report documents methodologic and computer software developed by Energy Division and Computer Sciences Division personnel at Oak Ridge National Laboratory (ORNL). The software is designed to quantify and automatically map geologic and other cost-related parameters as required to estimate coal mining costs. The software complements the detailed coal production cost models for both underground and surface mines which have been developed for the Electric Power Research Institute (EPRI) by NUS, Corp. These models require input variables such as coal seam thickness, coal seam depth, surface slope, etc., to estimate mining costs. This report provides a general overview of the software and methodology developed by ORNL to calculate some of these parameters along with sample map output which indicates the geographical distribution of these geologic characteristics. A detailed user guide for implementing the software has been prepared and is included in the appendixes. (Sample input data which may be used to verify the operation of the software are available from ORNL.) Also included is a brief review of coal production, coal recovery, and coal resource calculation studies. This system will be useful to utilities and coal mine operators alike in estimating costs through comprehensive assessment before mining takes place.
International Nuclear Information System (INIS)
This paper presents high accuracy tritium production rate measurement results compared with calculations using the MCNPX Monte Carlo particle transport code. The experimental results are regarded as reference values for a new passive technique based on the secondary charged particle activation method developed for measuring the tritium production rate in the test blanket modules of the ITER Tokamak. The 16O(t,n)18F reaction, which is one of the possible tritium monitor reactions, was also extensively investigated, and the experimentally determined reaction rates were compared with simulations. Li2CO3 solution was filled and sealed into quartz ampoules which were irradiated in the Training Reactor of the Budapest University of Technology and Economics. The amount of 18F was determined using γ-spectroscopy. Then the precise tritium measurements were carried out in the Hertelendi Laboratory of Environmental Studies using the 3H–3He ingrowth method, where the 3He produced during the storage time is measured by a static noble gas mass spectrometer (VG-5400). The HT/HTO ratio in the irradiated aqueous solutions was found to be 0.1323±0.0034. Based on the comparison of the measurements and the simulations it was pointed out that the model calculations underestimate the reaction rate of both the 6Li(n,t)α and the 16O(t,n)18F reactions by 5–10% and 15%, respectively. -- Highlights: ► Tritium measurements for verifying the 6Li6(n, t)α reaction rate calculated by MCNPX. ► The HT/HTO ratio was determined in the neutron irradiated aqueous solution of Li2CO3. ► The reaction rate of 16O(t,n)18F was measured in thermal neutron spectrum
Nuclear model calculation and targetry recipe for production of 110mIn
International Nuclear Information System (INIS)
110mIn is potentially an important positron emitting that can be used in positron emission tomography. In this work, the excitation functions and production yields of 110Cd(d, 2n), 111Cd(d, 3n), natCd(d, xn), 110Cd(p, n), 111Cd(p, 2n), 112Cd(p, 3n) and natCd(p, xn) reactions to produce the 110mIn were calculated using nuclear model code TALYS and compared with the experimental data. The yield of isomeric state production of 110In was also compared with ground state production ones to reach the optimal energy range of projectile for the high yield production of metastable state. The results indicate that the 110Cd(p, n)110mIn is a high yield reaction with an isomeric ratio (σm/σg) of about 35 within the optimal incident energy range of 15–5 MeV. To make the target, cadmium was electroplated on a copper substrate in varying electroplating conditions such as PH, DC current density, temperature and time. A set of cold tests were also performed on the final sample under several thermal shocks to verify target resistance. The best electroplated cadmium target was irradiated with 15 MeV protons at current of 100 µA for one hour and the production yield of 110mIn and other byproducts were measured. - Highlights: • Optimization of a cadmium electroplating bath to produce high yield 110mIn. • Influence of targetry on isomeric cross section ratio 110mIn/110gIn. • Activity measurement for natCd(p, xn)110m,110g,111g,114mIn reactions
Associated ZH production at hadron colliders: The fully differential NNLO QCD calculation
International Nuclear Information System (INIS)
We consider Standard Model Higgs boson production in association with a Z boson in hadron collisions. We present a fully exclusive computation of QCD radiative corrections up to next-to-next-to-leading order (NNLO). Our calculation includes the Higgs boson decay to bottom quarks (b) in next-to-leading order QCD and the leptonic decay of the Z boson with finite-width effects and spin correlations. The computation is implemented in a parton level Monte Carlo program that makes possible to consider arbitrary kinematical cuts on the final-state leptons, the b jets and the associated QCD radiation, and to compute the corresponding distributions in the form of bin histograms. We assess the impact of QCD radiative effects in the boosted kinematics at the LHC and show that the inclusion of the NNLO corrections is crucial to control the pT spectrum of the Higgs boson candidate
Comparison of optics and electronics for the calculation of matrix-vector products
Gary, C. K.
1992-01-01
Optical processors are attractive because of their ability to perform massively parallel operations such as matrix vector products. The inherently analog nature of optical calculations requires that optical processors be based on analog computations. While the speed at which such analog operations can be performed as well as the natural parallelism of optical systems are great advantages of optical processors, the analog representation of values severely limits the achievable accuracy. Furthermore, optical processors are limited by the need to convert information to and from the intensity of light. Digitization can be used to increase the accuracy of optical matrix-vector processors, but causes a severe reduction in speed. This paper compares the throughput and power requirements of optical and electronic processors, showing that optical matrix-vector processors can provide a greater number of operations/Watt than conventional electronics.
Cross section calculations for subthreshold pion production in peripheral heavy-ion collisions
Norbury, J. W.; Cucinotta, F. A.; Deutchman, P. A.; Townsend, L. W.
1986-01-01
Total cross sections angular distributions, and spectral distributions for the exclusive production of charged and neutral subthreshold pions produced in peripheral nucleus-nucleus collisions are calculated by using a particle-hole formalism. The pions result from the formation and decay of an isobar giant resonance state formed in a C-12 nucleus. From considerations of angular momentum conservation and for the sake of providing a unique experimental signature, the other nucleus, chosen for this work to be C-12 also, is assumed to be excited to one of its isovector (1+) giant resonance states. The effects of nucleon recoil by the pion emission are included, and Pauli blocking and pion absorption effects are studied by varying the isobar width. Detailed comparisons with experimental subthreshold pion data for incident energies between 35 and 86 MeV/nucleon are made.
Calculation of the decay power of fission products considering neutron capture transformation
International Nuclear Information System (INIS)
The decay power of fission products has been calculated taking into consideration the neutron capture transformation of each nuclide and its beta decay. The nuclear data library contains 1114 nuclides of which 144 are stable. Neutron capture transformation is considered for 59 nuclides, 31 of which are stable. The atom number of each nuclide is calculated analytically with code DCHAIN. The effect of neutron capture transformation in the decay power of fission products was examined by varying the neutron spectrum, neutron flux, fissioning nuclide, and irradiation and cooling time. From the results obtained the following were revealed: The effect of neutron capture increases with neutron flux and irradiation time, and it becomes salient beyond 105 sec in cooling time. It is small for less than the 104 sec which is important in the design of ECCS (emergency core cooling system) of a light-water reactor. In this region the decay power changes are small, less than 0.2%, by the neutron capture for the thermal fission of 235U irradiated for one year to thermal neutron flux 3 x 1013 n/cm2/sec. The effect of neutron capture has peaks around cooling time 106 sec and 108 sec; it is negligible beyond 109 sec. The changes in decay power are 2.4%, 10.5% and 0.2% at cooling time 106 sec, 108 sec and 109 sec, respectively, in the above irradiation. Around 106 sec, the change in decay power is mainly from the contributions of 134Cs (17%), sup(148m)Pm(60%) and 148Pm(14%). Around 108 sec 134Cs(98%) alone contributes to the change in decay power. (author)
Status of theories for calculations of production cross sections of long-lived radionuclides
International Nuclear Information System (INIS)
The theories discussed in this paper are confined to those currently being used or considered for the calculation of activation cross sections. The theories are the same regardless of whether the activation product is long lived or short lived. However, the cross sections for the generation of long-lived radionuclides are more difficult or expensive to measure, hence there are fewer data available and the requirement on the predictive capability of the theories used is more stringent. It is clear from other papers presented in this meeting and the adjoining NEANDC specialists' meeting on activation cross sections that the nuclear theories of interest to this group are those used or needed in modern Hauser-Feshbach (H-F) codes with pre-equilibrium correction and gamma-ray cascades. The H-F formalism is indispensable due to the sensitivity of the calculated results, especially isomeric ratios, to the spins and parities of the discrete levels as well as to the spin distributions in the total and exciton level densities. Topics included in this paper are the optical model, gamma-ray strength function, total and exciton level-density theories, and the pre-compound model. In each subject, we describe the most commonly used theories first, followed by relatively new developments that are used in at least one model code or the promising theories that do not appear to require a large effort for incorporation into existing H-F codes. 14 refs
Indian Academy of Sciences (India)
O Scholten; A Usov
2010-08-01
To describe photo- and meson-induced reactions on the nucleon, one is faced with a rather extensive coupled-channel problem. Ignoring the effects of channel coupling, as one would do in describing a certain reaction at the tree level, invariably creates a large inconsistency between the different reactions that are described. In addition, the imaginary parts of the amplitude, which are related through the optical theorem, to total cross-sections, are directly reflected in certain polarization observables. Performing a full coupled-channel calculation thus offers the possibility to implement the maximum number of constraints. The drawback one is faced with is to arrive at a simultaneous fit of a large number of reaction channels. While some of the parameters are common to many reactions, one is still faced with the challenge to optimize a large number of parameters in a highly non-linear calculation. Here we show that such an approach is possible and present some results for photoinduced strangeness production.
International Nuclear Information System (INIS)
Intense neutron fluxes within fusion reactors that are currently being designed will lead to the activation of structural components, and to assess and minimize this radioactivity, nuclear cross sections are needed for neutrons with energies up to 20 MeV. We describe research performed for the International Atomic Energy Agency (IAEA) Coordinated Research Programme on activation cross sections for fusion reactor technology, which has selected certain high-priority reactions for both experimental and theoretical study. Using statistical model codes, we have investigated excitation function cross sections for radionuclide production in the reactions 94Mo(n,p)94Nb, 109Ag(n,2n)108mAg, 151Eu(n,2n)150m Eu, 153Eu(n,2n)152g+m2Eu, 159Tb(n,2n)158Tb, 187Re(n,2n)186mRe, 179Hf(n,2n)178m2Hf, 193Ir(n,2n)192m2Ir. Using our calculated results for the excitation functions, along with calculations by other groups, the theoretical excitation functions have been normalized to experimental values at 14.5 MeV to produce evaluated excitation functions. These evaluations can be used within radiation transport and nuclide inventory codes to design, and assess the environmental impact of, fusion reactors. 23 refs., 4 figs., 1 tab
Luong, Anh D; Schaubroeck, Thomas; Dewulf, Jo; De Laender, Frederik
2015-10-01
The environmental impacts of biomass harvesting can be quantified through the amount of net primary production required to produce one unit of harvested biomass (SPPR-specific primary production required). This paper presents a new calculation framework that explicitly takes into account full food web complexity and shows that the resulting SPPR for toothed whales in the Icelandic marine ecosystem is 2.8 times higher than the existing approach based on food web simplification. In addition, we show that our new framework can be coupled to food web modeling to examine how uncertainty on ecological data and processes can be accounted for while estimating SPPR. This approach reveals that an increase in the degree of heterotrophy by flagellates from 0% to 100% results in a two-fold increase in SPPR estimates in the Barents Sea. It also shows that the estimated SPPR is between 3.9 (herring) and 5.0 (capelin) times higher than that estimated when adopting food chain theory. SPPR resulting from our new approach is only valid for the given time period for which the food web is modeled and cannot be used to infer changes in SPPR when the food web is altered by changes in human exploitation or environmental changes. PMID:26348118
Harbers, Jasper V; Huijbregts, Mark A J; Posthuma, Leo; Van de Meent, Dik
2006-03-01
Although many chemicals are in use, the environmental impacts of only a few have been established, usually on per-chemical basis. Uncertainty remains about the overall impact of chemicals. This paper estimates combined toxic pressure on coastal North Sea ecosystems from 343 high-production-volume chemicals used within the catchment of rivers Rhine, Meuse, and Scheldt. Multimedia fate modeling and species sensitivity distribution-based effects estimation are applied. Calculations start from production volumes and emission rates and use physicochemical substance properties and aquatic ecotoxicity data. Parameter uncertainty is addressed by Monte Carlo simulations. Results suggest that the procedure is technically feasible. Combined toxic pressure of all 343 chemicals in coastal North Seawater is 0.025 (2.5% of the species are exposed to concentration levels above EC50 values), with a wide confidence interval of nearly 0-1. This uncertainty appears to be largely due to uncertainties in interspecies variances of aquatic toxicities and, to a lesser extent, to uncertainties in emissions and degradation rates. Due to these uncertainties, the results support gross ranking of chemicals in categories: negligible and possibly relevant contributions only. With 95% confidence, 283 of the 343 chemicals (83%) contribute negligibly (less than 0.1%) to overall toxic pressure, and only 60 (17%) need further consideration. PMID:16568772
HyPEP-FY 07 Annual Report: A Hydrogen Production Plant Efficiency Calculation Program
Energy Technology Data Exchange (ETDEWEB)
Chang Oh
2007-09-01
The Very High Temperature Gas-Cooled Reactor (VHTR) coupled to the High Temperature Steam Electrolysis (HTSE) process is one of two reference integrated systems being investigated by the U.S. Department of Energy and Idaho National Laboratory for the production of hydrogen. In this concept the VHTR outlet temperature of 900 °C provides thermal energy and high efficiency electricity for the electrolysis of steam in the HTSE process. In the second reference system the Sulfur Iodine (SI) process is coupled to the VHTR to produce hydrogen thermochemically. In the HyPEP project we are investigating and characterizing these two reference systems with respect to production, operability, and safety performance criteria. Under production, plant configuration and working fluids are being studied for their effect on efficiency. Under operability, control strategies are being developed with the goal of maintaining equipment within operating limits while meeting changes in demand. Safety studies are to investigate plant response for equipment failures. Specific objectives in FY07 were (1) to develop HyPEP Beta and verification and validation (V&V) plan, (2) to perform steady state system integration, (3) to perform parametric studies with various working fluids and power conversion unit (PCU) configurations, (4) the study of design options such as pressure, temperature, etc. (5) to develop a control strategy and (6) to perform transient analyses for plant upsets, control strategy, etc for hydrogen plant with PCU. This report describes the progress made in FY07 in each of the above areas. (1) The HyPEP code numeric scheme and Graphic User Interface have been tested and refined since the release of the alpha version a year ago. (2) The optimal size and design condition for the intermediate heat exchanger, one of the most important components for integration of the VHTR and HTSE plants, was estimated. (3) Efficiency calculations were performed for a variety of working fluids for
Precision calculations for gauge-boson pair production with a hadronic jet at hadron colliders
Energy Technology Data Exchange (ETDEWEB)
Kallweit, Stefan
2008-11-21
Gauge-boson pair-production processes with an additional hadronic jet are of particular interest as background to Higgs and new-physics searches at hadron colliders. Moreover, they enable - besides genuine gauge-boson pair production - a direct analysis of the non-Abelian gauge-boson self-interactions in the electroweak sector. In this work we provide precision calculations for the processes pp/p anti p {yields} VV+jet+X. In detail, corrections to WW+jet, ZZ+jet, and WZ+jet production are evaluated at next-to-leading-order in the strong coupling (NLO QCD). Particular care has to be taken when treating the infrared singularities arising in the virtual and real corrections. The FormCalc/LoopTools package is applied for the virtual corrections, where dimensionally regularized infrared-divergent integrals are added to the FF library which is used for the regular ones. The real-emission matrix elements are evaluated in terms of helicity amplitudes in the Weyl--van-der-Waerden formalism. The Catani--Seymour dipole subtraction formalism mediates the cancellation of infrared divergences between the two contributions. To perform the numerical integration a multi-channel Monte Carlo integrator is written in C++, which is designed to meet the requirements of integrating cross sections in the dipole subtraction formalism. For all gauge-boson assignments, the NLO QCD corrections significantly stabilize the artificial dependence of the leading-order (LO) cross sections on renormalization and factorization scales for Tevatron. For LHC, however, only a modest reduction of the scale dependence results unless a veto on a second hard jet is applied. Beyond investigating the production processes, leptonic decays of the gauge bosons are considered. To this end, a full amplitude calculation including resonant and non-resonant contributions to the leptonic final states, a simple narrow-width approximation (NWA), and an improved version of the NWA that takes into account spin correlations
Precision calculations for gauge-boson pair production with a hadronic jet at hadron colliders
International Nuclear Information System (INIS)
Gauge-boson pair-production processes with an additional hadronic jet are of particular interest as background to Higgs and new-physics searches at hadron colliders. Moreover, they enable - besides genuine gauge-boson pair production - a direct analysis of the non-Abelian gauge-boson self-interactions in the electroweak sector. In this work we provide precision calculations for the processes pp/p anti p → VV+jet+X. In detail, corrections to WW+jet, ZZ+jet, and WZ+jet production are evaluated at next-to-leading-order in the strong coupling (NLO QCD). Particular care has to be taken when treating the infrared singularities arising in the virtual and real corrections. The FormCalc/LoopTools package is applied for the virtual corrections, where dimensionally regularized infrared-divergent integrals are added to the FF library which is used for the regular ones. The real-emission matrix elements are evaluated in terms of helicity amplitudes in the Weyl--van-der-Waerden formalism. The Catani--Seymour dipole subtraction formalism mediates the cancellation of infrared divergences between the two contributions. To perform the numerical integration a multi-channel Monte Carlo integrator is written in C++, which is designed to meet the requirements of integrating cross sections in the dipole subtraction formalism. For all gauge-boson assignments, the NLO QCD corrections significantly stabilize the artificial dependence of the leading-order (LO) cross sections on renormalization and factorization scales for Tevatron. For LHC, however, only a modest reduction of the scale dependence results unless a veto on a second hard jet is applied. Beyond investigating the production processes, leptonic decays of the gauge bosons are considered. To this end, a full amplitude calculation including resonant and non-resonant contributions to the leptonic final states, a simple narrow-width approximation (NWA), and an improved version of the NWA that takes into account spin correlations are
International Nuclear Information System (INIS)
In this paper, the magnetic reversal process, hysteresis loops and energy products for exchange-coupled Nd2Fe14B/α-Fe bilayers are studied systematically by a three-dimensional (3D) model. The 3D calculations are numerically solved using the finite difference method, where the results are carefully compared with those calculated by one-dimensional (1D) model. It is found that the calculated hysteresis loops and energy products based on the two methods are consistent with each other. Both nucleation fields and coercivities decrease monotonically as the soft layer thickness Ls increases. In addition, the calculated spatial distributions of magnetization orientations in the thickness direction at various applied fields based on both methods signify a three-step magnetic reversal process, which are nucleation, growth and displacement of the domain wall. The calculated magnetic orientations within the film plane, however, are totally different according to the two methods. The 3D calculation exhibits a process of vortex formation and annihilation. On the other hand, the 1D calculation gives a quasi-coherent one, where magnetization orientation is coherent in the film plane and varies in the thickness direction. This new reversal mechanism displayed in the film plane has a systematic influence on the nucleation fields, coercivity and energy products. - Highlights: • Consistent hysteresis loops and energy products for 3D and 1D calculation. • Domain wall formation, evolution and displacement perpendicular to the film plane. • Vortex formation, annihilation and better loop squareness in 3D calculation. • Larger nucleation fields, remanence and smaller coercivity in 3D calculation
EARLINET Single Calculus Chain - technical - Part 2: Calculation of optical products
Mattis, Ina; D'Amico, Giuseppe; Baars, Holger; Amodeo, Aldo; Madonna, Fabio; Iarlori, Marco
2016-07-01
In this paper we present the automated software tool ELDA (EARLINET Lidar Data Analyzer) for the retrieval of profiles of optical particle properties from lidar signals. This tool is one of the calculus modules of the EARLINET Single Calculus Chain (SCC) which allows for the analysis of the data of many different lidar systems of EARLINET in an automated, unsupervised way. ELDA delivers profiles of particle extinction coefficients from Raman signals as well as profiles of particle backscatter coefficients from combinations of Raman and elastic signals or from elastic signals only. Those analyses start from pre-processed signals which have already been corrected for background, range dependency and hardware specific effects. An expert group reviewed all algorithms and solutions for critical calculus subsystems which are used within EARLINET with respect to their applicability for automated retrievals. Those methods have been implemented in ELDA. Since the software was designed in a modular way, it is possible to add new or alternative methods in future. Most of the implemented algorithms are well known and well documented, but some methods have especially been developed for ELDA, e.g., automated vertical smoothing and temporal averaging or the handling of effective vertical resolution in the case of lidar ratio retrievals, or the merging of near-range and far-range products. The accuracy of the retrieved profiles was tested following the procedure of the EARLINET-ASOS algorithm inter-comparison exercise which is based on the analysis of synthetic signals. Mean deviations, mean relative deviations, and normalized root-mean-square deviations were calculated for all possible products and three height layers. In all cases, the deviations were clearly below the maximum allowed values according to the EARLINET quality requirements.
Wu, Yanlin; Shi, Jin; Chen, Hongche; Zhao, Jianfu; Dong, Wenbo
2016-10-01
4-tert-butylphenol (4-t-BP), an endocrine disrupting chemical, is widely distributed in natural bodies of water but is difficult to biodegrade. In this study, we focused on the transformation of 4-t-BP in photo-initiated degradation processes. The steady-state photolysis and laser flash photolysis (LFP) experiments were conducted in order to elucidate its degradation mechanism. Identification of products was performed using the GC-MS, LC-MS and theoretical calculation techniques. The oxidation pathway of 4-t-BP by hydroxyl radical (HO) was also studied and H2O2 was added to produce HO. 4-tert-butylcatechol and 4-tert-butylphenol dimer were produced in 4-t-BP direct photolysis. 4-tert-butylcatechol and hydroquinone were produced by the oxidation of HO. But the formation mechanism of 4-tert-butylcatechol in the two processes was different. The benzene ring was fractured in 4-t-BP oxidation process and 29% of TOC was degraded after 16h irradiation. PMID:27213674
Calculation of excitation functions for the production of Cu and Co medical isotopes
International Nuclear Information System (INIS)
Copper and cobalt radioisotopes have been used for both diagnostic and therapeutic purposes in the field of nuclear medicine. There is considerable interest in 60,61,64,67Cu and 55,57Co radioisotopes for some applications like PET, SPECT imaging and targeted radiotherapy of tumors. In present study, the production of 60,61,64,67Cu and 55,57Co via 64Zn(p,a)61Cu, 67Zn(p,a)64Cu, 70Zn(p,a)67Cu, 58Ni(p,a)55Co, 60Ni(p,a)57Co, 64Zn(p,na)60Cu and 68Zn(p,na)64Cu reactions have been investigated in the range of 5-40 MeV proton incident energy. The new version of the code ALICE-2011 is used to determine the excitation functions of these nuclear reactions. The calculated excitation functions were compared with experimental results and semi-empirical cross section values of a previously developed model. (orig.)
International Nuclear Information System (INIS)
Radcalc for Windows' is a menu-driven Microsoft2 Windows-compatible computer code that calculates the radiolytic production of hydrogen gas in high- and low-level radioactive waste. In addition, the code also determines US Department of Transportation (DOT) transportation classifications, calculates the activities of parent and daughter isotopes for a specified period of time, calculates decay heat, and calculates pressure buildup from the production of hydrogen gas in a given package geometry. Radcalc for Windows was developed by Packaging Engineering, Transportation and Packaging, Westinghouse Hanford Company, Richland, Washington, for the US Department of Energy (DOE). It is available from Packaging Engineering and is issued with a user's manual and a technical manual. The code has been verified and validated
International Nuclear Information System (INIS)
Highlights: ► We calculated the effects of ENDF libraries on gas production rates in structural material. ► We used the MCNPX-2.5.0 Monte Carlo code for three-dimensional calculations. ► The most prominent contributions to gas production rates are from Fe-56 and Fe-54 isotopes. ► Proton production was found greatest for JENDL-4.0 library with 409.69 appm/30 FPY. ► The helium limit of 500 appm is reached at 50 cm for all selected libraries. - Abstract: Proton and He-4 gas production rates in the structural material of a fusion-fission hybrid reactor were calculated with the three-dimensional Monte Carlo method by the MCNPX-2.5.0 code. We examined these reaction rates with five nuclear data libraries: ENDF/B-VII.0 T = 300 K, JEFF-3.1 T = 300 K, JENDL-4.0 T = 300 K, ROSFOND T = 300 K and CENDL-3.1 T = 300 K. The production from each isotope of structural material made of ferritic steel was calculated. The neutron flux load is assumed to be 10 MW/m2
Institute of Scientific and Technical Information of China (English)
WEN Zhigang; ZHU Dan; TANG Youjun; LI Yuquan; ZHANG Guorong
2005-01-01
Gas chromatography fingerprint technique has the advantages of fast performance and low cost. It can be used to conduct analysis without interruption either in the field or at laboratory. This technique has been used successfully in such cases that conventional production logging techniques are powerless. Taking low-concentration anthracene as internal standard, we calculated the absolute concentrations of fingerprints, initially made some experiments directly on biodegradation of crude oils, and calculated production allocation in the Gudong Oil field. Compared with the production logging, this method has made up for the deficiencies of the former GC fingerprint technique. It will find wide applications in monitoring the trend of production in various oil-fields.
SaiToh, Akira
2011-01-01
A C++ library, named ZKCM, has been developed for the purpose of multiprecision matrix calculations, which is based on the GNU MP and MPFR libraries. It is especially convenient for writing programs involving tensor-product operations, tracing-out operations, and singular-value decompositions. Its extension library, ZKCM_QC, for simulating quantum computing has been developed using the time-dependent matrix-product-state simulation method. This report gives a brief introduction to the libraries with sample programs.
International Nuclear Information System (INIS)
SOURCE 2.0 is a computer code being jointly developed within the Canadian nuclear industry. It will model the necessary mechanisms required to calculate the fission product release for a variety of accident scenarios, including large break loss of coolant accidents with or without emergency coolant injection. This paper presents the origin of SOURCE 2.0, describes the code structure, the fission product mechanisms modelled, and the quality assurance procedures that are being followed during the code's life cycle. (author)
Matrix product state calculations for one-dimensional quantum chains and quantum impurity models
International Nuclear Information System (INIS)
This thesis contributes to the field of strongly correlated electron systems with studies in two distinct fields thereof: the specific nature of correlations between electrons in one dimension and quantum quenches in quantum impurity problems. In general, strongly correlated systems are characterized in that their physical behaviour needs to be described in terms of a many-body description, i.e. interactions correlate all particles in a complex way. The challenge is that the Hilbert space in a many-body theory is exponentially large in the number of particles. Thus, when no analytic solution is available - which is typically the case - it is necessary to find a way to somehow circumvent the problem of such huge Hilbert spaces. Therefore, the connection between the two studies comes from our numerical treatment: they are tackled by the density matrix renormalization group (DMRG) and the numerical renormalization group (NRG), respectively, both based on matrix product states. The first project presented in this thesis addresses the problem of numerically finding the dominant correlations in quantum lattice models in an unbiased way, i.e. without using prior knowledge of the model at hand. A useful concept for this task is the correlation density matrix (CDM) which contains all correlations between two clusters of lattice sites. We show how to extract from the CDM, a survey of the relative strengths of the system's correlations in different symmetry sectors as well as detailed information on the operators carrying long-range correlations and the spatial dependence of their correlation functions. We demonstrate this by a DMRG study of a one-dimensional spinless extended Hubbard model, while emphasizing that the proposed analysis of the CDM is not restricted to one dimension. The second project presented in this thesis is motivated by two phenomena under ongoing experimental and theoretical investigation in the context of quantum impurity models: optical absorption
Matrix product state calculations for one-dimensional quantum chains and quantum impurity models
Energy Technology Data Exchange (ETDEWEB)
Muender, Wolfgang
2011-09-28
This thesis contributes to the field of strongly correlated electron systems with studies in two distinct fields thereof: the specific nature of correlations between electrons in one dimension and quantum quenches in quantum impurity problems. In general, strongly correlated systems are characterized in that their physical behaviour needs to be described in terms of a many-body description, i.e. interactions correlate all particles in a complex way. The challenge is that the Hilbert space in a many-body theory is exponentially large in the number of particles. Thus, when no analytic solution is available - which is typically the case - it is necessary to find a way to somehow circumvent the problem of such huge Hilbert spaces. Therefore, the connection between the two studies comes from our numerical treatment: they are tackled by the density matrix renormalization group (DMRG) and the numerical renormalization group (NRG), respectively, both based on matrix product states. The first project presented in this thesis addresses the problem of numerically finding the dominant correlations in quantum lattice models in an unbiased way, i.e. without using prior knowledge of the model at hand. A useful concept for this task is the correlation density matrix (CDM) which contains all correlations between two clusters of lattice sites. We show how to extract from the CDM, a survey of the relative strengths of the system's correlations in different symmetry sectors as well as detailed information on the operators carrying long-range correlations and the spatial dependence of their correlation functions. We demonstrate this by a DMRG study of a one-dimensional spinless extended Hubbard model, while emphasizing that the proposed analysis of the CDM is not restricted to one dimension. The second project presented in this thesis is motivated by two phenomena under ongoing experimental and theoretical investigation in the context of quantum impurity models: optical absorption
A simple method for evaluation of uncertainties in fission product decay heat summation calculations
International Nuclear Information System (INIS)
The present precision of nuclear data for the aggregate decay heat evaluation is analyzed quantitatively for 50 fissioning systems. In the practical calculation, a simple approximate method is proposed in order to avoid complication of the calculation and to point out easily the main causal nuclei of the uncertainties in decay heat calculations. As for the independent yield, the correlation among the values is taken into account. For this evaluation, nuclear data and their uncertainty data are taken from ENDF/B-VI nuclear data library. (author)
2010-07-01
... Human Services that applicant did not act with due diligence; (iii) One-half the number of days... extension for a human drug, antibiotic drug or human biological product. 1.775 Section 1.775 Patents... Review § 1.775 Calculation of patent term extension for a human drug, antibiotic drug or human...
International Nuclear Information System (INIS)
A method for the approximate calculation of the composition of the detonation products of gas mixtures is reported in the paper. The method is based on the assumption of partial equilibrium in the subsystem of biomolecular reactions. The description of the equilibrium composition in the subsystem of biomolecular reactions is reduced to the solution of the system of linear equations
Energy Technology Data Exchange (ETDEWEB)
Bernnat, W.; Keinert, J.; Mattes, M. [Inst. for Nuclear Energy and Energy Systems, Univ. of Stuttgart, Stuttgart (Germany)
2004-03-01
For the calculation of neutron spectra in cold and super thermal sources scattering laws for a variety of liquid and solid cyrogenic materials were evaluated and prepared for use in deterministic and Monte Carlo transport calculations. For moderator materials like liquid and solid H{sub 2}O, liquid He, liquid D{sub 2}O, liquid and solid H{sub 2} and D{sub 2}, solid CH{sub 4} and structure materials such as Al, Bi, Pb, ZrHx, and graphite scattering law data and cross sections are available. The evaluated data were validated by comparison with measured cross sections and comparison of measured and calculated neutron spectra as far as available. Further applications are the calculation of production and transport and storing of ultra cold neutrons (UCN) in different UCN sources. The data structures of the evaluated data are prepared for the common S{sub N}-transport codes and the Monte Carlo Code MCNP. (orig.)
International Nuclear Information System (INIS)
For the calculation of neutron spectra in cold and super thermal sources scattering laws for a variety of liquid and solid cyrogenic materials were evaluated and prepared for use in deterministic and Monte Carlo transport calculations. For moderator materials like liquid and solid H2O, liquid He, liquid D2O, liquid and solid H2 and D2, solid CH4 and structure materials such as Al, Bi, Pb, ZrHx, and graphite scattering law data and cross sections are available. The evaluated data were validated by comparison with measured cross sections and comparison of measured and calculated neutron spectra as far as available. Further applications are the calculation of production and transport and storing of ultra cold neutrons (UCN) in different UCN sources. The data structures of the evaluated data are prepared for the common SN-transport codes and the Monte Carlo Code MCNP. (orig.)
Calculation of fission product behavior in a multiple reactor barriers in case of an accident
International Nuclear Information System (INIS)
Radiation protection of the population in case of a reactor accident utilizes reference levels which are based on doses values. Therefore, adequate provisions for effective and timely dose assessment for population in case of accidents at nuclear power plant (NPP) are important. Developing the background for such provisions is the objective of this study. In particular, an exponential model has been developed and utilized to calculate the release rate of the most volatile gaseous materials from different reactor barriers. Calculation has been performed for noble gases (133Xe, 135Xe, 138Xe, 85Kr, 87Kr, 88Kr) and the halogens(1'31I, 132I, 133I, 1'34I, 135I). The effective dose rate equivalent is calculations in the nearly stage of a reactor accident. Calculations are performed using the MCNP-4C code. The results are comparable with the final analysis report which utilizes different codes. Results of our calculation shows no excessive dose in populated regions and it is recommended to use secondary containment barrier for highly reduction of the release rate to the environment. (Author)
International Nuclear Information System (INIS)
Highlights: ► Production of 153Sm isotope by neutron activation in a nuclear reactor was studied. ► Optimal parameters for weight and irradiation time were found. ► This study led to an empirical correction factor (kf). ► Kf enhanced the production procedure of the 153Sm radioisotope. ► The results led to nearly 60% decrease in the amount of material used in the production process. - Abstract: The feasibility of producing 2000–3000 mCi 153Sm by irradiation of 152Sm in 5 MW TRR was studied via TRR core simulation. In this study the cross-section of 152Sm (n,γ) 153Sm reaction from ENDF/B library was used. The effective activation cross section for production of 153Sm is obtained using the neutron spectra in different irradiation channel of the core. The activity of the simulated samples is calculated using the obtained fluxes and cross sections. Then samples were prepared and irradiated under different conditions and fluxes. The final production’s specific activity was measured by the standard dose calibrator ISOMED 1010. By comparison of the theoretical calculations and actual measurements, an empirical correction factor (Kf) was obtained, which is helpful in production procedure of the 153Sm radioisotope. The optimal weight of the samples and irradiation time was studied according to the flux calculations based on the location of the sample and saturated activity calculation. In order to test the proposed conditions, samples were prepared and were irradiated under the proposed conditions. According to the compared results with the initial irradiation condition, the new proposed sample which weighed 4 mg of Sm2O3 is acceptable for the labeling, therefore this study led to nearly 60% decrease in the amount of material used in the production process
Directory of Open Access Journals (Sweden)
NIKOLA KILIBARDA
2000-11-01
Full Text Available An adequate method for calculating chemical equilibrium in a predominantly gaseous, multi-component reactive mixture was investigated and successfully applied. This method involves the stated equilibrium reaction scheme, including, first, the formation of chemical species, of which concentrations prevail in the mixture, then the formation of gaseous atomic species by dissociation of previous ones, and, finally, the formation of complex chemical species from the atomic species. A computer program, which permits calculations of equilibrium compositions by the iteration procedure, has been developed. The results of calculations have been compared with data obtained by the programs OPHELIE, MICROPEP, and the program SPP, as documented in the NASA-Lewis Code, which is presently the world-wide standard. All comparisons gave satisfactory agreement.
A novel method to calculate solar UV exposure relevant to vitamin D production in humans.
Seckmeyer, Gunther; Schrempf, Michael; Wieczorek, Anna; Riechelmann, Stefan; Graw, Kathrin; Seckmeyer, Stefan; Zankl, Maria
2013-01-01
We present a novel method to calculate vitamin D3 -weighted exposure by integrating the incident solar spectral radiance over all relevant parts of the human body. Earlier investigations are based on the irradiance on surfaces, whereas our calculated exposure of a voxel model of a human takes into account the complex geometry of the radiation field. Assuming that sufficient vitamin D3 (1000 international units) can be produced within the human body in one minute for a completely uncovered body in vertical posture in summer at midlatitudes (e.g. Rome, June 21, noon, UV index of 10), we calculate the exposure times needed in other situations or seasons to gain enough vitamin D3 . Our calculations show that the UV index is not a good indicator for the exposure which depends on the orientation of the body (e.g. vertical (standing) or horizontal (lying down) posture). Without clothing the exposure is dominated by diffuse sky radiation and it is nearly irrelevant how the body in vertical posture is oriented toward the sun. At the winter solstice (December 21, noon, cloudy) at least in central Europe sufficient vitamin D3 cannot be obtained with realistic clothing, even if the exposure were extended to all daylight hours. PMID:23517086
International Nuclear Information System (INIS)
It is presented the absorption-production nodal method for steady and dynamical calculations in one-dimension and one group energy. It was elaborated the NOD1D computer code (in FORTRAN-IV language). Calculations of neutron flux and power distributions, burnup, effective multiplication factors and critical boron concentration were made with the NOD1D code and compared with results obtained through the CITATION code, which uses the finite difference method. The nuclear constants were produced by the LEOPARD code. (M.C.K.)
Duchemin, C; Guertin, A; Haddad, F; Michel, N; Métivier, V
2015-09-01
HIGHLIGHTS • Production of Sc-44 m, Sc-44 g and contaminants. • Experimental values determined using the stacked-foil technique. • Thick-Target production Yield (TTY) calculations. • Comparison with the TALYS code version 1.6.Among the large number of radionuclides of medical interest, Sc-44 is promising for PET imaging. Either the ground-state Sc-44 g or the metastable-state Sc-44 m can be used for such applications, depending on the molecule used as vector. This study compares the production rates of both Sc-44 states, when protons or deuterons are used as projectiles on an enriched Calcium-44 target. This work presents the first set of data for the deuteron route. The results are compared with the TALYS code. The Thick-Target production Yields of Sc-44 m and Sc-44 g are calculated and compared with those for the proton route for three different scenarios: the production of Sc-44 g for conventional PET imaging, its production for the new 3 γ imaging technique developed at the SUBATECH laboratory and the production of a Sc-44 m/Sc-44 g in vivo generator for antibody labelling. PMID:26301533
International Nuclear Information System (INIS)
Objective: The existing solid target production method of radiometals requires high capital and operational expenditures, which limit the production of radiometals to the small fraction of cyclotron facilities that are equipped with solid target systems. Our objective is to develop a robust solution target method, which can be applicable to a wide array of radiometals and would be simply and easily adopted by existing cyclotron facilities for the routine production of radiometals. Method: We have developed a simplified, solution target approach for production of 89Zr using a niobium target by 14 MeV energy proton bombardment of aqueous solutions of yttrium salts via the 89Y(p,n)89Zr nuclear reaction. The production conditions were optimized, following a detailed mechanistic study of the gas evolution. Results: Although the solution target approach avoided the expense and complication of solid target processing, rapid radiolytic formation of gases in the target represents a major impediment in the success of solution target. To address this challenge we performed a systematic mechanistic study of gas evolution. Gas evolution was found to be predominantly due to decomposition of water to molecular hydrogen and oxygen. The rate of gas evolutions varied > 40-fold depending on solution composition even under the same irradiation condition. With chloride salts, the rate of gas evolution increased in the order rank Na < Ca < Y. However, the trend was reversed with the corresponding nitrate salts, and further addition of nitric acid to the irradiating solution minimized gas evolution. At optimized condition, 89Zr was produced in moderate yield (4.36 ± 0.48 MBq/μA•h) and high effective specific activity (464 ± 215 MBq/μg) using the solution target approach (2.75 M yttrium nitrate, 1.5 N HNO3, 2 h irradiation at 20 μA). Conclusion: The novel findings on substrate dependent, radiation-induced water decomposition provide fundamental data for the development and
Shielding calculation of a hot cell for the processing of fission products
International Nuclear Information System (INIS)
A dose rate estimation is made for an operator of a lead wall, fission products processing hot cell, in a distance of 50 cm from the emission source, at Brazilian Institute of Nuclear Engineering (IEN). (L.C.J.A.)
The Production Function Methodology for Calculating Potential Growth Rates & Output Gaps
Karel Havik; Kieran Mc Morrow; Fabrice Orlandi; Christophe Planas; Rafal Raciborski; Werner Roeger; Alessandro Rossi; Anna Thum-Thysen; Valerie Vandermeulen
2014-01-01
This paper provides a detailed description of the current version of the Ecofin Council approved production function (PF) methodology which is used for assessing both the productive capacity (i.e. potential output) and cyclical position (i.e. output gaps) of EU economies. Compared with the previous 2010 paper on the same topic, there have been two significant changes to the PF methodology, namely an overhaul of the NAWRU methodology & the introduction of a new T+10 methodology.
Delayed neutron spectra and their uncertainties in fission product summation calculations
Energy Technology Data Exchange (ETDEWEB)
Miyazono, T.; Sagisaka, M.; Ohta, H.; Oyamatsu, K.; Tamaki, M. [Nagoya Univ. (Japan)
1997-03-01
Uncertainties in delayed neutron summation calculations are evaluated with ENDF/B-VI for 50 fissioning systems. As the first step, uncertainty calculations are performed for the aggregate delayed neutron activity with the same approximate method as proposed previously for the decay heat uncertainty analyses. Typical uncertainty values are about 6-14% for {sup 238}U(F) and about 13-23% for {sup 243}Am(F) at cooling times 0.1-100 (s). These values are typically 2-3 times larger than those in decay heat at the same cooling times. For aggregate delayed neutron spectra, the uncertainties would be larger than those for the delayed neutron activity because much more information about the nuclear structure is still necessary. (author)
Hencken, Kai; Trautmann, Dirk; Baur, Gerhard
1998-01-01
We present a calculation of higher order effects for the impact parameter dependent probability for single and multiple electron-positron pairs in (peripheral) relativistic heavy ion collisions. Also total cross sections are given for SPS and RHIC energies. We make use of the expression derived recently by several groups where the summation of all higher orders can be done analytically in the high energy limit. An astonishing result is that the cross section, that is, integrating over all imp...
Žagar, Tomaž; Božič, Matjaž; Ravnik, Matjaž
2004-12-01
In this paper, a process of long-lived activity determination in research reactor concrete shielding is presented. The described process is a combination of experiment and calculations. Samples of original heavy reactor concrete containing mineral barite were irradiated inside the reactor shielding to measure its long-lived induced radioactivity. The most active long-lived (γ emitting) radioactive nuclides in the concrete were found to be 133Ba, 60Co and 152Eu. Neutron flux, activation rates and concrete activity were calculated for actual shield geometry for different irradiation and cooling times using TORT and ORIGEN codes. Experimental results of flux and activity measurements showed good agreement with the results of calculations. Volume of activated concrete waste after reactor decommissioning was estimated for particular case of Jožef Stefan Institute TRIGA reactor. It was observed that the clearance levels of some important long-lived isotopes typical for barite concrete (e.g. 133Ba, 41Ca) are not included in the IAEA and EU basic safety standards.
International Nuclear Information System (INIS)
The Nitinol stent was bombarded in a cyclotron at a flux rate of 4 μA/cm2 to produce 48V via 48Ti (p, n) 48V reaction. In this study dose distribution of 48V radioactive stent was investigated for renal arteries. Version X-2.6 of the MCNP Monte Carlo radiation transport system code was employed to calculate dose distribution around the stent. As 48V is a mixed gamma and beta particle emitter, two separate runs of MCNP for both beta and gamma particles were performed and the total deposited dose was acquired by adding the two mentioned values. In order to verify the simulation, the calculated results have been compared with previous published data for the source. Calculated results show high dose gradient near the stent and the maximum amount of dose deposits at the vessel wall. According to (AAPM) TG-60/149 protocol, the dosimetric parameters, including geometry function, G(ρ,z), radial dose function, g L (ρ), and anisotropy function, F(ρ,z), were also determined. (author)
International Nuclear Information System (INIS)
Yield-weighted average cross sections of neutron radiative capture, (n,2n), and (n,3n) reactions over prompt fission products (FPs) from 235U and 239Pu are calculated. The prompt fission production yields are taken from the ENDF/B-VII.0 library. The FPs for each fissile material exist over a range of approximately 1000 neutron-rich nuclides. Several nuclear reaction codes are utilized for calculating the cross sections on each individual fission product - EMPIRE-2.19, TALYS-1.0, GNASH, and CoH. The influence of the FP isomers on the average cross sections is examined with TALYS. We investigate the dependence of the average cross sections on the number of FPs taken for averaging. It is shown that the average capture cross section is much more sensitive to the number of FPs included, compared with the (n,2n) and (n,3n) reactions. An intercomparison of the calculated cross sections with the different reaction codes is carried out. In the capture reaction, EMPIRE predicted lower cross section than TALYS and CoH owing to different default assumptions used in the γ-ray strength function modeling. Moreover, the pre-equilibrium models implemented in each code give different predictions for the neutron-emission reactions, although the differences are relatively small. We also discuss a difference between the macroscopic and microscopic calculation options in TALYS for the pre-equilibrium model, optical potential model, and γ-ray strength function. The predictive capability of the reaction codes for the capture reaction is examined by comparing their calculations with the ENDF data, which are based on measurements. Compared with the historic Foster and Arthur's evaluation, our new (n,2n) predictions are similar, although our capture predictions are almost an order of magnitude higher. Recommended cross sections for use in applications have been tabulated in ENDF-formatted files. (author)
Energy Technology Data Exchange (ETDEWEB)
Salmon, R.; Hermann, O.W.
1992-10-01
The rate of neutron production from ([alpha], n) reactions in canisters of immobilized high-level waste containing borosilicate glass or glass-ceramic compositions is significant and must be considered when estimating neutron shielding requirements. The personal computer program ALPHA calculates the ([alpha], n) neutron production rate of a canister of vitrified high-level waste. The user supplies the chemical composition of the glass or glass-ceramic and the curies of the alpha-emitting actinides present. The output of the program gives the ([alpha], n) neutron production of each actinide in neutrons per second and the total for the canister. The ([alpha], n) neutron production rates are source terms only; that is, they are production rates within the glass and do not take into account the shielding effect of the glass. For a given glass composition, the user can calculate up to eight cases simultaneously; these cases are based on the same glass composition but contain different quantities of actinides per canister. In a typical application, these cases might represent the same canister of vitrified high-level waste at eight different decay times. Run time for a typical problem containing 20 chemical species, 24 actinides, and 8 decay times was 35 s on an IBM AT personal computer. Results of an example based on an expected canister composition at the Defense Waste Processing Facility are shown.
ALPHN: A computer program for calculating (α, n) neutron production in canisters of high-level waste
International Nuclear Information System (INIS)
The rate of neutron production from (α, n) reactions in canisters of immobilized high-level waste containing borosilicate glass or glass-ceramic compositions is significant and must be considered when estimating neutron shielding requirements. The personal computer program ALPHA calculates the (α, n) neutron production rate of a canister of vitrified high-level waste. The user supplies the chemical composition of the glass or glass-ceramic and the curies of the alpha-emitting actinides present. The output of the program gives the (α, n) neutron production of each actinide in neutrons per second and the total for the canister. The (α, n) neutron production rates are source terms only; that is, they are production rates within the glass and do not take into account the shielding effect of the glass. For a given glass composition, the user can calculate up to eight cases simultaneously; these cases are based on the same glass composition but contain different quantities of actinides per canister. In a typical application, these cases might represent the same canister of vitrified high-level waste at eight different decay times. Run time for a typical problem containing 20 chemical species, 24 actinides, and 8 decay times was 35 s on an IBM AT personal computer. Results of an example based on an expected canister composition at the Defense Waste Processing Facility are shown
A function to calculate all relative prime numbers up to the product of the first n primes
Schmitt, Matthias
2014-01-01
We prove an isomorphism between the finite domain from 1 up to the product of the first n primes and the new defined set of prime modular numbers. This definition provides some insights about relative prime numbers. We provide an inverse function from the prime modular numbers into this finite domain. With this function we can calculate all numbers from 1 up to the product of the first n primes that are not divisible by the first n primes. This function provides a non sequential way for the c...
Kivimäe, Caroline
2007-01-01
This thesis focus on the carbon and oxygen fluxes in the Barents and Norwegian Seas and presents four studies where the main topics are variability of biological production, air-sea exchange and budget calculations. The world ocean is the largest short term reservoir of carbon on Earth, consequently it has the potential to control the atmospheric concentrations of carbon dioxide (CO2) and has already taken up ~50 % of the antropogenically emitted CO2. It is thus important to...
International Nuclear Information System (INIS)
The 123Te(p,n)123I, 124Te(p,n)124I and 124Te(p,2n)123I reactions, among the many reaction channels opened, are the major reactions under consideration from a diagnostic purpose because reaction residuals as the gamma emitters are used for most radiopharmaceutical applications involving radioiodine. Based on the available experimental data, the absorption cross sections and elastic scattering angular distributions of the proton-induced nuclear reaction on Te isotopes below 60 NeV are calculated using the optical model code APMNK. The transmission coefficients of neutron, proton, deuteron, trition and alpha particles are calculated by CUNF code and are fed into the GNASH code. By adjusting level density parameters and the pair correction values of some reaction channels, as well as the composite nucleus state density constants of the pre-equilibrium model, the production cross sections and energy-angle correlated spectra of the secondary light particles, as well as production cross sections and energy distributions of heavy recoils and gamma rays are calculated by the statistical plus pre-equilibrium model code GNAH. The calculated results are analysed and compared with the experimental data taken from the EXFOR. The optimized global optical model parameters give overall agreement with the experimental data over both the entire energy range and all tellurium isotopes. (author)
FAYE SOUPOURMAS; DUNCAN IRONMONGER
2002-01-01
This paper presents estimates for a thirty year period of Australia’s Gross Household Product (GHP), the economic value added by unpaid labour and the households own capital. In 2000 GHP was estimated to be worth $471 billion. Gross Market Product (GDP minus the imputed value of owner-occupied housing) was worth $604 billion in 2000. The household economy was nearly 80 per cent of the size of the market economy in 2000. More importantly, the GHP is nearly half (44%) of total economic activity...
Directory of Open Access Journals (Sweden)
Avsec Jurij
2014-01-01
Full Text Available Hydrogen is one of the most promising energy sources of the future enabling direct production of power and heat in fuel cells, hydrogen engines or furnaces with hydrogen burners. One of the last remainder problems in hydrogen technology is how to produce a sufficient amount of cheap hydrogen. One of the best options is large scale thermochemical production of hydrogen in combination with nuclear power plant. copper-chlorine (CuCl cycle is the most promissible thermochemical cycle to produce cheap hydrogen.This paper focuses on a CuCl cycle, and the describes the models how to calculate thermodynamic properties. Unfortunately, for many components in CuCl cycle the thermochemical functions of state have never been measured. This is the reason that we have tried to calculate some very important thermophysical properties. This paper discusses the mathematical model for computing the thermodynamic properties for pure substances and their mixtures such as CuCl, HCl, Cu2OCl2 important in CuCl hydrogen production in their fluid and solid phase with an aid of statistical thermodynamics. For the solid phase, we have developed the mathematical model for the calculation of thermodynamic properties for polyatomic crystals. In this way, we have used Debye functions and Einstein function for acoustical modes and optical modes of vibrations to take into account vibration of atoms. The influence of intermolecular energy we have solved on the basis of Murnaghan equation of state and statistical thermodynamics.
Pilot application of PalmGHG, the RSPO greenhouse gas calculator for oil palm products
Bessou, Cécile; Chase, Laurence D. C.; Henson, Ian E.; Abdul-Manan, Amir F.N.; Milà I Canals, Llorenç; Agus, Fahmuddin; Sharma, Mukesh; Chin, Melissa
2014-01-01
The Roundtable on Sustainable Palm Oil (RSPO) is a non-profit association promoting sustainable palm oil through a voluntary certification scheme. Two successive science-based working groups on greenhouse gas (GHG) were active in RSPO from 2009 to 2011, with the aim of identifying ways of achieving meaningful and verifiable reductions of GHG emissions. One of the outputs of the second group is PalmGHG, a GHG calculator using the life cycle assessment ap-proach to quantify major sources of emi...
PalmGHG, the RSPO greenhouse gas calculator for oil palm products
Bessou, Cécile; Chase, Laurence; Henson, Ian; Amir F. N. Abdul-Manan; Milà-I-Canals, Llorenç; Agus, Fahmuddin; Sharma, Mukesh
2012-01-01
The Roundtable on Sustainable Palm Oil (RSPO) is a non-profit association promoting sustainable palm oil through a voluntary certi-fication scheme. Two successive science-based working groups on greenhouse gas (GHG) have been active in RSPO between 2009-2011, with the aim of identifying ways leading to meaningful and verifiable reduction of GHG emissions. One of the outputs is PalmGHG, a GHG calculator using the LCA approach to quantify the major sources of emission and sequestration for a mi...
Calculation of charged fusion product distributions in space, energy, and time
International Nuclear Information System (INIS)
The equation for the radial diffusion and slowing down of fast ions in a plasma is solved by a finite-difference technique. The terms included are ion source, radial diffusion, electron and ion drag. From the ion density at the radial boundary, the loss flux is calculated and used to model the signals in a lost-ion diagnostic. The code is also used to model the density of α-particles in future DT experiments. This information is used to predict the features to be seen by alpha diagnostics
International Nuclear Information System (INIS)
Igneous rock successions can be investigated with respect to their genetic coherence or to the role in fractional crystallization during their generation, respectively, by evaluating element concentration correlations. It is shown that the existence of a linear relation between element concentrations or their logarithms is only a necessary, but not a sufficient condition for fractional crystallization as the dominating factor of graduating element concentrations. The comparison of the slope of such correlation lines with the slope calculated on the basis of the distribution coefficients evaluated by using Schuetze's 18O index reveals whether fractional crystallization is dominant in graduating element concentrations in igneous rocks. Several applications are given. (author)
Monte Carlo calculations of pair production in high-intensity laser-plasma interactions
Duclous, Roland; Kirk, John; Bell, Anthony
2010-01-01
Gamma-ray and electron-positron pair production will figure prominently in laser-plasma experiments with next generation lasers. Using a Monte Carlo approach we show that straggling effects arising from the finite recoil an electron experiences when it emits a high energy photon, increase the number of pairs produced on further interaction with the laser fields.
Weak production and electroproduction of δ(1236) in a Zucker-model calculation
International Nuclear Information System (INIS)
Zucker's model for weak production and electroproduction of δ(1236) is reconsidered in the light of recent experimental data. We find that the disagreement between the predictions of the Zucker model and the experimental data can be significantly reduced by choosing a different form for #betta# exchange
Weak production and electroproduction of Δ(1236) in a Zucker-model calculation
Choudhury, S. Rai; Dewan, H. K.
1983-07-01
Zucker's model for weak production and electroproduction of Δ(1236) is reconsidered in the light of recent experimental data. We find that the disagreement between the predictions of the Zucker model and the experimental data can be significantly reduced by choosing a different form for ω exchange.
Use of ELOCA.Mk5 to calculate transient fission product release from CANDU fuel elements
International Nuclear Information System (INIS)
A change in fuel element power output, or a change in heat transfer conditions, will result in an immediate change in the temperature distribution in a fuel element. The temperature distribution change will be accompanied by concomitant changes in fuel stress distribution that lead, in turn, to a release of fission products to the fuel-to-sheath gap. It is important to know the inventory of fission products in the fuel-to-sheath gap, because this inventory is a major component of the source term for many postulated reactor accidents. ELOCA.Mk5 is a FORTRAN-77 computer code that has been developed to estimate transient releases to the fuel-to-sheath gap in CANDU reactors. ELOCA.Mk5 is an integration of the FREEDOM fission product release model into the ELOCA fuel element thermo-mechanical code. The integration of FREEDOM into ELOCA allows ELOCA.Mk5 to model the feedback mechanisms between the fission product release and the thermo-mechanical response of the fuel element. This paper describes the physical model, gives details of the ELOCA.Mkt code, and describes the validation of the model. We demonstrate that the model gives good agreement with experimental results for both steady state and transient conditions
International Nuclear Information System (INIS)
A study of Λ production has been made in the target fragmentation region from pp interactions at 360 GeV/c. The triple Regge analysis of the double differential distribution d2N/d(M2/s)dt led to an estimate of the kaon trajectory intercept as approx.=-0.6. Comparison of the double and single inclusive distributions supports the idea of Pomeron factorization. The charged multiplicities and moments from virtual 'K+'p interactions have been studied as a function of M, the c.m. energy of the virtual 'K+'p system. The results agree reasonably well with the on shell K+p data. (orig.)
Nuclear model calculations on the production of {sup 119}Sb via various nuclear reactions
Energy Technology Data Exchange (ETDEWEB)
Sadeghi, Mahdi, E-mail: msadeghi@nrcam.org [Agricultural, Medical and Industrial Research School, Nuclear Science and Technology Research Institute, P.O. Box 31485/498, Karaj (Iran, Islamic Republic of); Enferadi, Milad [Research and Science Branch, Islamic Azad University, Tehran (Iran, Islamic Republic of)
2011-04-15
Only very few radionuclides exist that decay exclusively by EC-mode without accompanying radiation, {sup 119}Sb is one of them. Auger emitter {sup 119}Sb (T{sub 1/2} = 38.9 h, I{sub EC} = 100%) is a potent nuclide for targeted radionuclide therapy based on theoretical dosimetry calculations at a subcellular scale. Auger electron emitting radionuclides in cancer therapy offer the opportunity to deliver a high radiation dose to the tumor cells with high radiotoxicity while minimizing toxicity to normal tissue. {sup 119}Sb excitation function via {sup 119}Sn(p,n){sup 119}Sb, {sup 120}Sn(p,2n){sup 119}Sb, {sup 121}Sb(p,3n){sup 119}Te {yields} {sup 119}Sb, {sup 122}Sn(p,4n){sup 119}Sb, {sup 119}Sn(d,2n){sup 119}Sb and {sup 117}Sn({alpha},2n){sup 119}Te {yields} {sup 119}Sb reactions were calculated by ALICE/91, ALICE/ASH (GDH Model and Hybrid Model) and TALYS-1.0 (equilibrium and pre-equilibrium) codes. Requisite thicknesses of targets were obtained by SRIM code for each reaction.
Nuclear model calculations on the production of 119Sb via various nuclear reactions
International Nuclear Information System (INIS)
Only very few radionuclides exist that decay exclusively by EC-mode without accompanying radiation, 119Sb is one of them. Auger emitter 119Sb (T1/2 = 38.9 h, IEC = 100%) is a potent nuclide for targeted radionuclide therapy based on theoretical dosimetry calculations at a subcellular scale. Auger electron emitting radionuclides in cancer therapy offer the opportunity to deliver a high radiation dose to the tumor cells with high radiotoxicity while minimizing toxicity to normal tissue. 119Sb excitation function via 119Sn(p,n)119Sb, 120Sn(p,2n)119Sb, 121Sb(p,3n)119Te → 119Sb, 122Sn(p,4n)119Sb, 119Sn(d,2n)119Sb and 117Sn(α,2n)119Te → 119Sb reactions were calculated by ALICE/91, ALICE/ASH (GDH Model and Hybrid Model) and TALYS-1.0 (equilibrium and pre-equilibrium) codes. Requisite thicknesses of targets were obtained by SRIM code for each reaction.
Calculation of iridium-192 production for radiography using G.A. Siwabessy reactor
International Nuclear Information System (INIS)
Iridium-In is one of the radioisotopes used in gamma radiography. Calculation for producing iridium-In using G.A. Siwabessy nuclear reactor has been carried out. The targets were discs with 2.7 mm in diameter and 0.15 mm in thickness. The neutron flux was the value at the central irradiation position as high as 1.3 x 1014 n.s-1.cm-2. Calculation results showed that iridium metal irradiation for 12 days resulted in iridium-192 with radioactivity of 96.8 GBq per disc at the end of irradiation. If the irradiation was continued to the next irradiation period after 16 days of shut down, the irradiation resulted in 171.2 GBq of iridium-In. If the target was irradiated continuously for 40 days, the irradiation resulted in 284.5 GBq of iridium-192. The resulted radionuclide impurity was iridium-194 which decayed rapidly with half life of 19.15 hours. The initial radioactivity required for effective radiation source for gamma radiography was 3700 GBq in a radiation source. If the target was irradiated with shut down, the discs required in a radiation sources were 24 discs. If the target was irradiated continuously, the required discs were 14 discs in a radiation source. (author)
International Nuclear Information System (INIS)
The production of l91Pt and l88Pt by cyclotron irradiation can be carried out by direct reactions using α and proton beams on osmium and iridium targets respectively. The lack of data in the literature concerning the excitation functions for these nuclear reactions makes the optimization of the irradiation parameters impossible. This report includes a review of the few nuclear data available in the literature, some theoretical predictions about the beam energy necessary for the production of the two radioisotopes of interest and the results of some preliminary irradiations carried out with the variable energy cyclotron of JRC-Ispra (VA, Italy) of the EU at three different energies: 35 MeV for protons, 22 and 33 MeV for α particles
Quantitative Calculations for Black Hole Production at the Large Hadron Collider
Bock, Nicolas
2008-01-01
The framework of Large Extra Dimensions provides a way to explain why gravity is weaker compared to the other forces in nature. A consequence of this model is the possible production of D-dimensional Black Holes in high energy p-p collisions at the Large Hadron Collider. The present work uses the CATFISH Black Hole generator to study quantitatively how these events could be observed in the hadronic channel at mid-rapidity using a particle tracking detector.
Analytical formulas for calculation of K X-ray production cross sections by alpha ions
International Nuclear Information System (INIS)
In the present study, different procedures are followed to deduce the semi-empirical and the empirical K X-rayX-ray production cross sections induced by alpha ions from the available experimental data and the theoretical results of the ECPSSR model for elements with 20≤Z≤30. The deduced K X-ray production cross sections are compared with predictions from ECPSSR model and with other earlier works. Generally, the deduced K X-ray production cross sections obtained by fitting the available experimental data for each element separately give the most reliable values than those obtained by a global fit. - Highlights: ► The results were presented for elements with atomic numbers 20≤Z≤30 by alpha impact. ► The present semi-empirical formulas were derived from both theoretical and experimental values. ► The available experimental data are directly fitted to deduce the empirical one. ► The results obtained for each element separately give the most reliable values than those obtained by a global fit. ► This procedure is proposed as a black-box way to quickly estimate the cross section.
International Nuclear Information System (INIS)
The energy ranges of prime interest for LWR's, FBR's, and MFE's are quite different, the low eV region for LWR's, the keV region for FBR's, and around 14 MeV for MFE's. Yet although the energy range is wide, the statistical model of nuclear reactions works well for most of the dosimetry and gas production needs. Even at 15 MeV where the predictions of the model are compared against experiments performed by Atomics International and Lawrence Livermore Laboratory the model works well
SPARC-90: A code for calculating fission product capture in suppression pools
International Nuclear Information System (INIS)
This report describes the technical bases and use of two updated versions of a computer code initially developed to serve as a tool for calculating aerosol particle retention in boiling water reactor (BWR) pressure suppression pools during severe accidents, SPARC-87 and SPARC-90. The most recent version is SPARC-90. The initial or prototype version (Owczarski, Postma, and Schreck 1985) was improved to include the following: rigorous treatment of local particle deposition velocities on the surface of oblate spherical bubbles, new correlations for hydrodynamic behavior of bubble swarms, models for aerosol particle growth, both mechanistic and empirical models for vent exit region scrubbing, specific models for hydrodynamics of bubble breakup at various vent types, and models for capture of vapor iodine species. A complete user's guide is provided for SPARC-90 (along with SPARC-87). A code description, code operating instructions, partial code listing, examples of the use of SPARC-90, and summaries of experimental data comparison studies also support the use of SPARC-90. 29 refs., 4 figs., 11 tabs
Neutronic calculations of cold neutron intensity in a He chamber for ultra cold neutron production
International Nuclear Information System (INIS)
Neutronic optimization studies were performed to get highest cold neutron intensity in a He-II chamber for ultra cold neutron (UCN) production as a UCN source to be installed at a spallation neutron source. Main components of the system studied were Pb-Bi target shield system, graphite reflector, D2O thermal moderator, D2 cold moderator and He-II UCN source. Effect of the size of these components on cold neutron intensity and on heat deposition was studied under the condition of 600 MeV proton energy and 20 μA proton current. It was found that in the limitation of 1 W heat removal of the He cryostat we would obtain a cold neutron average flux of 7x1011 (n/cm2/sec) in the He chamber. (authors)
International Nuclear Information System (INIS)
Based on the Fick's law the computer program FPDR has been developed to calculate the one-dimensional diffusion and release behavior of fission products in the graphite sleeves of the first and second OGL-1 fuel assembly. Through the comparison between the measured and calculated penetration profiles, the diffusion coefficient of 90Sr in the first fuel sleeve has been estimated to be (2 -- 5) x 10-13 m2/s; those of 137Cs and 90Sr in the second fuel sleeve around or larger than 1 x 10-12 m2/s, and --10-14 m2/s, respectively. The release of 90Sr from the second fuel sleeve is negligible; that of 137Cs depends linearly on its diffusion coefficient if the coefficient is larger than 10-12 m2/s, but practically does not depend on its evaporation parameter. (author)
Energy Technology Data Exchange (ETDEWEB)
Mueller, S; Dunn, JB; Wang, M (Energy Systems); (Univ. of Illinois at Chicago)
2012-06-07
The Carbon Calculator for Land Use Change from Biofuels Production (CCLUB) calculates carbon emissions from land use change (LUC) for four different ethanol production pathways including corn grain ethanol and cellulosic ethanol from corn stover, miscanthus, and switchgrass. This document discusses the version of CCLUB released May 31, 2012 which includes corn, as did the previous CCLUB version, and three cellulosic feedstocks: corn stover, miscanthus, and switchgrass. CCLUB calculations are based upon two data sets: land change areas and above- and below-ground carbon content. Table 1 identifies where these data are stored and used within the CCLUB model, which is built in MS Excel. Land change area data is from Purdue University's Global Trade Analysis Project (GTAP) model, a computable general equilibrium (CGE) economic model. Section 2 describes the GTAP data CCLUB uses and how these data were modified to reflect shrubland transitions. Feedstock- and spatially-explicit below-ground carbon content data for the United States were generated with a surrogate model for CENTURY's soil organic carbon sub-model (Kwon and Hudson 2010) as described in Section 3. CENTURY is a soil organic matter model developed by Parton et al. (1987). The previous CCLUB version used more coarse domestic carbon emission factors. Above-ground non-soil carbon content data for forest ecosystems was sourced from the USDA/NCIAS Carbon Online Estimator (COLE) as explained in Section 4. We discuss emission factors used for calculation of international greenhouse gas (GHG) emissions in Section 5. Temporal issues associated with modeling LUC emissions are the topic of Section 6. Finally, in Section 7 we provide a step-by-step guide to using CCLUB and obtaining results.
International Nuclear Information System (INIS)
We review recent developments in the QCD description of jet production and modification in reactions with heavy nuclei at relativistic energies. Our goal is to formulate a perturbative expansion in the presence of nuclear matter that allows to systematically improve the accuracy of the theoretical predictions. As an example, we present calculations of inclusive jet cross sections at RHIC, Z0/γ*-tagged jet cross sections at the LHC, and jet shapes that include both next-to-leading order perturbative effects and the effects of the nuclear medium. (author)
Institute of Scientific and Technical Information of China (English)
Sohan Kumar GHIMIRE; Mukand Singh BABEL
2004-01-01
This study verifies the applicability of EPIC model for an erosion plot (61.2 m2) and anupland terraced watershed (72 ha) using a total of 94 rainfall events over a study period of two years.In order to analyze the effect of storm size on runoff and soil loss processes,rainfall events are divided into three groups:small (＜25mm),moderate (25-50mm) and large (＞50mm).Results indicate that the model could predict reasonably well the runoff and soil loss from the erosion plot and the watershed for the moderate and large rainfall events.However,the runoff and soil loss prediction for the small rainfall events is found to be poor.On annual basis,both surface runoffand soil loss predictions match well the observations.In light of the importance of the moderate and large rainfall events in producing most of the annual runoff and soil loss in the study area,the EPIC model is applied to assess the impacts of erosion on agricultural productivity and to evaluate management practices to protect watersheds in the middle mountainous area of Nepal.
International Nuclear Information System (INIS)
This report describes the calculation procedure of the TRANCS code, which deals with fission product transport in fuel rod of high temperature gas-cooled reactor (HTGR). The fundamental equation modeled in the code is a cylindrical one-dimensional diffusion equation with generation and decay terms, and the non-stationary solution of the equation is obtained numerically by a finite difference method. The generation terms consist of the diffusional release from coated fuel particles, recoil release from outer-most coating layer of the fuel particle and generation due to contaminating uranium in the graphite matrix of the fuel compact. The decay term deals with neutron capture as well as beta decay. Factors affecting the computation error has been examined, and further extention of the code has been discussed in the fields of radial transport of fission products from graphite sleeve into coolant helium gas and axial transport in the fuel rod. (author)
Śpiewanowski, M D; Horbatsch, M; Kirchner, T
2016-01-01
Inner-shell vacancy production for the O$^{8+}$-Li collision system at 1.5 MeV/amu is studied theoretically. The theory combines single-electron amplitudes for each electron in the system to extract multielectron information about the collision process. Doubly-differential cross sections obtained in this way are then compared with the recent experimental data by LaForge et al. [J. Phys. B 46, 031001 (2013)] yielding good resemblance, especially for low outgoing electron energy. A careful analysis of the processes that contribute to inner-shell vacancy production shows that the improvement of the results as compared to single-active-electron calculations can be attributed to the leading role of two-electron excitation-ionization processes.
Leclerc, Arnaud
2014-01-01
We propose an iterative method for computing vibrational spectra that significantly reduces the memory cost of calculations. It uses a direct product primitive basis, but does not require storing vectors with as many components as there are product basis functions. Wavefunctions are represented in a basis each of whose functions is a sum of products (SOP) and the factorizable structure of the Hamiltonian is exploited. If the factors of the SOP basis functions are properly chosen, wavefunctions are linear combinations of a small number of SOP basis functions. The SOP basis functions are generated using a shifted block power method. The factors are refined with a rank reduction algorithm to cap the number of terms in a SOP basis function. The ideas are tested on a 20-D model Hamiltonian and a realistic CH$_3$CN (12 dimensional) potential. For the 20-D problem, to use a standard direct product iterative approach one would need to store vectors with about $10^{20}$ components and would hence require about $8 \\tim...
Directory of Open Access Journals (Sweden)
J. Kaiser
2011-10-01
Full Text Available The comment by Nicholson (2011a questions the "consistency" of the "definition" of the "biological end-member" used by Kaiser (2011a in the calculation of oxygen gross production. "Biological end-member" refers to the relative oxygen isotope ratio difference between photosynthetic oxygen and Air-O_{2} (abbreviated ^{17}δ_{P} and ^{18}δ_{P} for ^{17}O/^{16}O and ^{18}O/^{16}O, respectively.
This comment has no merit for the following reasons: (a the isotopic composition of photosynthetic oxygen cannot be "defined", it can only be measured, modelled or calculated based on other data; (b the isotopic composition of photosynthetic oxygen was not "defined" in Kaiser (2011a, but derived from published measurements; (c the published measurements themselves were inconsistent and no single result could be identified as best; (d since no best value could be identified, a hypothetical base case was constructed in a way that was consistent with previous publications; (e the values of ^{17}δ_{P}=−11.646‰ and ^{18}δ_{P}=−22.835‰ assumed for the base case are compatible with the experimental evidence published before the paper of Kaiser (2011a; (f even if the "biological end-member" was based on a definition, there could be no argument about the "consistency" of this definition – as per its nature, a definition is arbitrary.
The qualification of base case gross production values as being "30 % too high" must therefore also be rejected. Even though recently revised measurements of the relative ^{17}O/^{16}O isotope ratio difference between VSMOW and Air-O_{2}, ^{17}δ_{VSMOW} (Barkan and Luz, 2011, do support lower estimates of gross production, our own measurements disagree with these revised ^{17}δ_{VSMOW} values. If scaled for differences in ^{18
}
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Sargsyan Samvel Volodyaevich
2014-09-01
Full Text Available Fire-resistance testing laboratory for building products and constructions is a production room with a substantial excess heat (over 23 W/m . Significant sources of heat inside the aforementioned laboratory are firing furnace, designed to simulate high temperature effects on structures and products of various types in case of fire development. The excess heat production in the laboratory during the tests is due to firing furnaces. The laboratory room is considered as an object consisting of two control volumes (CV, in each of which there may be air intake and air removal, pollutant absorption or emission. In modeling air exchange conditions the following processes are being considered: the processes connected with air movement in the laboratory room: the jet stream in a confined space, distribution of air parameters, air motion and impurity diffusion in the ventilated room. General upward ventilation seems to be the most rational due to impossibility of using local exhaust ventilation. It is connected with the peculiarities of technological processes in the laboratory. Air jets spouted through large-perforated surface mounted at the height of 2 m from the floor level, "flood" the lower control volume, entrained by natural convective currents from heat sources upward and removed from the upper area. In order to take advantage of the proposed method of the required air exchange calculation, you must enter additional conditions, taking into account the provision of sanitary-hygienic characteristics of the current at the entrance of the service (work area. Exhaust air containing pollutants (combustion products, is expelled into the atmosphere by vertical jet discharge. Dividing ventilated rooms into two control volumes allows describing the research process in a ventilated room more accurately and finding the air exchange in the lab room during the tests on a more reasonable basis, allowing to provide safe working conditions for the staff without
Zayed, M. A.; Hawash, M. F.; Fahmey, M. A.; El-Habeeb, Abeer A.
2007-11-01
Sertraline (C 17H 17Cl 2N) as an antidepressant drug was investigated using thermal analysis (TA) measurements (TG/DTG and DTA) in comparison with electron impact (EI) mass spectral (MS) fragmentation at 70 eV. Semi-empirical MO-calculations, using PM3 procedure, has been carried out on neutral molecule and positively charged species. These calculations included bond length, bond order, bond strain, partial charge distribution and heats of formation (Δ Hf). Also, in the present work sertraline-iodine product was prepared and its structure was investigated using elemental analyses, IR, 1H NMR, 13C NMR, MS and TA. It was also subjected to molecular orbital calculations (MOC) in order to confirm its fragmentation behavior by both MS and TA in comparison with the sertraline parent drug. In MS of sertraline the initial rupture occurred was CH 3NH 2+ fragment ion via H-rearrangement while in sertraline-iodine product the initial rupture was due to the loss of I + and/or HI + fragment ions followed by CH 2dbnd NH + fragment ion loss. In thermal analyses (TA) the initial rupture in sertraline is due to the loss of C 6H 3Cl 2 followed by the loss of CH 3-NH forming tetraline molecule which thermally decomposed to give C 4H 8, C 6H 6 or the loss of H 2 forming naphthalene molecule which thermally sublimated. In sertraline-iodine product as a daughter the initial thermal rupture is due to successive loss of HI and CH 3NH followed by the loss of C 6H 5HI and HCl. Sertraline biological activity increases with the introduction of iodine into its skeleton. The activities of the drug and its daughter are mainly depend upon their fragmentation to give their metabolites in vivo systems, which are very similar to the identified fragments in both MS and TA. The importance of the present work is also due to the decision of the possible mechanism of fragmentation of the drug and its daughter and its confirmation by MOC.
International Nuclear Information System (INIS)
In the field of tritium and fusion blanket technology possibly an important and early contribution to the development of a fusion reactor blanket can be obtained by irradiation experiments at the research reactor FRJ-2 in Juelich, Federal Republic of Germany. However, the tritium production rate of 0.2 x 1013 to 2 x 1013 cm-3s-1 and the power per volume of 2 to 20 W cm-3 characteristic for a fusion reactor blanket have to be realized. The present report shows the reachable tritium values calculated for different irradiation positions in the FRJ-2 for natural lithium as a breeder material considering the actual existing neutron spectrum. Based on these results we come to the conclusion that the specified blanket data can actually be reached and adjusted. Therefore irradiation experiments at the FRJ-2 would be able to supply basical results for the fusion blanket development. (orig.)
ZZ ORYX-E/38B, Group Constant Library from ENDF/B Fission Product Data for ORIGEN Calculation
International Nuclear Information System (INIS)
1 - Nature of physical problem solved: Format: ORIGEN; Number of groups: 124 energy groups; Nuclides: H, He, Li, Be, B, C, N, O, F, Ne, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Zn, Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lu, Hf, Ta, W, Re, Os, Ir, Pt, Au, Hg, Tl, Pb, Bi, Po. Origin: ENDF/B-IV; Weighting spectrum: Maxwellian (1/E) fission spectrum with a one percent tolerance. ORYX-E increases the versatility of the program ORIGEN , the isotope generation and depletion code package by providing basic cross section and decay information for light element, fission-product, and actinide nuclides. This data library package results from data compiled for ORNL Chemical Technology Division's work with ORIGEN and from a 2-year effort of the cross section evaluation working group (CSEWG) fission product task force. 2 - Method of solution: The data is generated from ENDF/B-IV and is formatted for input to the ORIGEN code. Applications include calculations for waste projection, decay heat, nuclear safeguards, and fuel cycle economics. The data library is generated from the ENDF/B-IV fission product data. The capture cross section of all fission product nuclides for which capture cross section information is given (about 180 nuclides) were processed into 124 energy groups using MINX. Multigroup cross sections were generated at 0 degrees with infinite dilution and one broad thermal group. Fine group data was generated using a Maxwellian (1/E) fission spectrum with a one percent tolerance
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Full text: this work is part of developing an analytical method for solving the neutrons transport equation in improving the treatment of the anisotropy of neutron scattering through heterogeneous shielding. We also develop the tools necessary for the formation of multigroup libraries (cross section) with the best choice of the weighting function. Among the radioprotection problems of radioisotopes production experiments in the research reactor core is mainly the photons gamma generation produced by radiative capture: activation of samples and their capsules. So, in order to review the safety of operating personnel and the public is essential to quantify the neutrons flux and gamma photons produced. In this study a numerical methods is used in two different Fortran program to solve the neutron transport problem and to determine the neutron and photon flux. This program based on the Monte Carlo method: the neutron is born with a unit statistical weight, this corrected after each imposed scattering event during its whole history within the shield. The final neutron statistical weight is used in an appropriate estimator to determine the searched response. The generated gamma rays by neutron capture are calculated of different isotopes, and then the equivalent dose rate is evaluated in biological tissue for different neutron source energies. We have identified and studied the choice of the best weighting function to calculate a library of multigroup cross sections self protected by using the energy weighting function. A Fortran program is used as a mathematical tool to solve the neutron slowing down equation in infinite homogeneous medium for different dilutions. We determined the energetic flux distribution and the effective integrals. The results of both calculations are in a good agreement; the relative error is less than 0.5%.
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Radon and its progenies in the atmosphere of normal working- and living-rooms contribute to parts of the respiratory tract the highest radiation load from all the natural radioactive environment. The base of todays calculations are the lung model of the ICRP-task groups and the physiological data of the ICRP-Reference Man. Both deal extensively with the problems associated with the adult but much less consideration is given to the physiological properties of the growing organism and the resulting radiation load. Functions for age dependent parameters, comprising geometrical dimensions of lung parts as well as respiratory standards were defined. With the use of a hybrid-computer the modifying influence of several parameters of the ICRP-lung model was investigated for the compartmental deposition of decay products as well as clearance effects. Furthermore typical daily routines for various ages, ranging from newborn to adult, comprising different activities, such resting, light and heavy work and times spent indoors and outdoors were considered; this shows great influence on the minute volume. Considering all these factors dose assessments were performed, which reveiled that the doses in the respiratory tract reach a maximum value for the age between 5 and 10 years. These values exceed the corresponding dose values for adults by factors of 2 and more. Dose calculations are presented for children of various ages and compared with those of male and female adults with different life patterns
Directory of Open Access Journals (Sweden)
J. Kaiser
2012-08-01
Full Text Available The comment by Nicholson (2011a questions the "consistency" of the "definition" of the "biological end-member" used by Kaiser (2011a in the calculation of oxygen gross production. "Biological end-member" refers to the relative oxygen isotope ratio difference between photosynthetic oxygen and Air-O_{2} (abbreviated ^{17}δ_{P} and ^{18}δ_{P} for ^{17}O/^{16}O and ^{18}O/^{16}O, respectively. The comment claims that this leads to an overestimate of the discrepancy between previous studies and that the resulting gross production rates are "30% too high". Nicholson recognises the improved accuracy of Kaiser's direct calculation ("dual-delta" method compared to previous approximate approaches based on ^{17}O excess (^{17}Δ and its simplicity compared to previous iterative calculation methods. Although he correctly points out that differences in the normalised gross production rate (g are largely due to different input parameters used in Kaiser's "base case" and previous studies, he does not acknowledge Kaiser's observation that iterative and dual-delta calculation methods give exactly the same g for the same input parameters (disregarding kinetic isotope fractionation during air-sea exchange. The comment is based on misunderstandings with respect to the "base case" ^{17}δ_{P} and ^{18}δ_{P} values. Since direct measurements of ^{17}δ_{P} and ^{18}δ_{P}do not exist or have been lost, Kaiser constructed the "base case" in a way that was consistent and compatible with literature data. Nicholson showed that an alternative reconstruction of ^{17}δ_{P} gives g values closer to previous studies. However, unlike Nicholson, we refrain from interpreting either reconstruction as a benchmark for the accuracy of g. A number of publications over the last 12 months
Ott, Lesley E.
2010-02-18
A three-dimensional (3-D) cloud-scale chemical transport model that includes a parameterized source of lightning NOx on the basis of observed flash rates has been used to simulate six midlatitude and subtropical thunderstorms observed during four field projects. Production per intracloud (PIC) and cloud-to-ground (PCG) flash is estimated by assuming various values of PIC and PCG for each storm and determining which production scenario yields NOx mixing ratios that compare most favorably with in-cloud aircraft observations. We obtain a mean PCG value of 500 moles NO (7 kg N) per flash. The results of this analysis also suggest that on average, PIC may be nearly equal to PCG, which is contrary to the common assumption that intracloud flashes are significantly less productive of NO than are cloud-to-ground flashes. This study also presents vertical profiles of the mass of lightning NOx after convection based on 3-D cloud-scale model simulations. The results suggest that following convection, a large percentage of lightning NOx remains in the middle and upper troposphere where it originated, while only a small percentage is found near the surface. The results of this work differ from profiles calculated from 2-D cloud-scale model simulations with a simpler lightning parameterization that were peaked near the surface and in the upper troposphere (referred to as a “C-shaped” profile). The new model results (a backward C-shaped profile) suggest that chemical transport models that assume a C-shaped vertical profile of lightning NOx mass may place too much mass near the surface and too little in the middle troposphere.
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Artun, Ozan, E-mail: ozanartun@yahoo.com; Aytekin, Hüseyin, E-mail: huseyinaytekin@gmail.com
2015-02-15
In this work, the excitation functions for production of medical radioisotopes {sup 122–125}I with proton, alpha, and deuteron induced reactions were calculated by two different level density models. For the nuclear model calculations, the Talys 1.6 code were used, which is the latest version of Talys code series. Calculations of excitation functions for production of the {sup 122–125}I isotopes were carried out by using the generalized superfluid model (GSM) and Fermi-gas model (FGM). The results have shown that generalized superfluid model is more successful than Fermi-gas model in explaining the experimental results.
International Nuclear Information System (INIS)
Despite of the renewed willing to accept nuclear power as a mean of mitigate the climate changing, to deal with the long lived waste still cause some concerning in relation to maintain in safety condition, during so many years. A technological solution to overcome this leg of time is to use a facility that burn these waste, besides to generate electricity. This is the idea built in the accelerator driven systems (ADS). This technology is being though to use some minor actinides (MAs) as fuel. This work presents a program to assess actinide concentrations, aiming a fertile-free fuel to be used in the future ADS technology. For that, use was made of a numerical code to solve the steady-state multigroup diffusion equation 3D to calculate the neutron fluxes, coupled it with a new code to solve, also numerically, depletion equations, named ACTRAN code. This paper shows the simulation of a PWR core during the residence time of the nuclear fuel, for three years, and after, for almost four hundred years, to assess the MAs production. The results show some insight in the best management to get a minimum amount of some MAs to use in the future generations of ADS. (author)
International Nuclear Information System (INIS)
The computer program, TRANCS, has been developed for evaluating the fractional release of long-lived fission products from coated fuel particles. This code numerically gives the non-stationary solution of the diffusion equation with birth and decay terms. The birth term deals with the fissile material in the fuel kernel, the contamination in the coating layers and the fission-recoil transfer from the kernel into the buffer layer; and the decay term deals with effective decay not only due to beta decay but also due to neutron capture, if appropriate input data are given. The code calculates the concentration profile, the release to birth rates (R/B), and the release and residual fractions in the coated fuel particle. Results obtained numerically have been in good agreement with the corresponding analytical solutions after the Booth model. Thus, the validity of the present code was confirmed, and further undate of the code has been discussed for extention of its computation scopes and models. (author)
Directory of Open Access Journals (Sweden)
Sekizawa Kazuyuki
2015-01-01
Full Text Available We present a microscopic calculation of multi-nucleon transfer reactions employing the time-dependent Hartree-Fock (TDHF theory. In our previous publication [Phys. Rev. C 88, 014614 (2013], we reported our analysis for the multi-nucleon transfer processes for several systems. Here we discuss effects of particle evaporation processes on the production cross sections. Since particle evaporation processes may not be described adequately by the TDHF calculations, we evaluate them using a statistical model. As an input of the statistical model, excitation energies of the final fragments are necessary. We evaluate them from the TDHF wave function after collisions, extending the particle number projection technique. From the calculation, the particle evaporation effects are found to improve descriptions of the production cross sections. However, the production cross sections are still underestimated for processes where a number of protons are transferred. Possible origins of the discrepancy are discussed.
Mihai BERCA; Roxana HOROIAŞ
2013-01-01
The Pedoclimatic Index (PCI) calculated by us is the product between the Aridity Index (AR) and the soil fertility status expressed through number of creditworthiness points (CWS – Creditworthiness of Soil): PCI = AR x CWS .Was used AR calculated after UNEP (United Nations Environment Programme) instead of the older De Martonne index. Determinations were performed in 6 different pedoclimatic areas, in which PCI has varied from 12 to 47. Taking into account that AR varies between 0,20 and 1,00...
International Nuclear Information System (INIS)
Excitation functions for the production of radionuclides Cs, Xe, I, Pb, Tl, Bi and some others for charged particle energies ranging from 5-100 MeV have been calculated. The well known experimental results have been compared to excitation functions calculated by two versions of the most widely used computer code ALICE. The generalized superfluid model of nuclei was used for level density description. The results of calculation for the ALICE-87 and ALICE-92 codes are discussed. Modified ALICE-92 code takes into account γ-ray competition, as well as cluster's preequilibrium emission. 43 refs.; 29 figs.; 3 tabs
International Nuclear Information System (INIS)
The computer codes FRESCO-I, FRESCO-II, PANAMA and SPATRA developed at Forschungszentrum Jülich in Germany in the early 1980s are essential tools to predict the fission product release from spherical fuel elements and the TRISO fuel performance, respectively, under given normal or accidental conditions. These codes are able to calculate a conservative estimation of the source term, i.e. quantity and duration of radionuclide release. Recently, these codes have been reversed engineered, modernized (FORTRAN 95/2003) and combined to form a consistent code named STACY (Source Term Analysis Code System). STACY will later become a module of the V/HTR Code Package (HCP). In addition, further improvements have been implemented to enable more detailed calculations. For example the distinct temperature profile along the pebble radius is now taken into account and coated particle failure rates can be calculated under normal operating conditions. In addition, the absolute fission product release of an V/HTR pebble bed core can be calculated by using the newly developed burnup code Topological Nuclide Transformation (TNT) replacing the former rudimentary approach. As a new functionality, spatially resolved fission product release calculations for normal operating conditions as well as accident conditions can be performed. In case of a full-core calculation, a large number of individual pebbles which follow a random path through the reactor core can be simulated. The history of the individual pebble is recorded, too. Main input data such as spatially resolved neutron fluxes and fluid dynamics data are provided by the VSOP code. Capabilities of the FRESCO-I and SPATRA code which allow for the simulation of the redistribution of fission products within the primary circuit and the deposition of fission products on graphitic and metallic surfaces are also available in STACY. In this paper, details of the STACY model and first results for its application to the 200 MW(th) HTR
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Xhonneux, Andre, E-mail: a.xhonneux@fz-juelich.de [Forschungszentrum Jülich, 52425 Jülich (Germany); Institute for Reactor Safety and Reactor Technology RWTH-Aachen, 52064 Aachen (Germany); Allelein, Hans-Josef [Forschungszentrum Jülich, 52425 Jülich (Germany); Institute for Reactor Safety and Reactor Technology RWTH-Aachen, 52064 Aachen (Germany)
2014-05-01
The computer codes FRESCO-I, FRESCO-II, PANAMA and SPATRA developed at Forschungszentrum Jülich in Germany in the early 1980s are essential tools to predict the fission product release from spherical fuel elements and the TRISO fuel performance, respectively, under given normal or accidental conditions. These codes are able to calculate a conservative estimation of the source term, i.e. quantity and duration of radionuclide release. Recently, these codes have been reversed engineered, modernized (FORTRAN 95/2003) and combined to form a consistent code named STACY (Source Term Analysis Code System). STACY will later become a module of the V/HTR Code Package (HCP). In addition, further improvements have been implemented to enable more detailed calculations. For example the distinct temperature profile along the pebble radius is now taken into account and coated particle failure rates can be calculated under normal operating conditions. In addition, the absolute fission product release of an V/HTR pebble bed core can be calculated by using the newly developed burnup code Topological Nuclide Transformation (TNT) replacing the former rudimentary approach. As a new functionality, spatially resolved fission product release calculations for normal operating conditions as well as accident conditions can be performed. In case of a full-core calculation, a large number of individual pebbles which follow a random path through the reactor core can be simulated. The history of the individual pebble is recorded, too. Main input data such as spatially resolved neutron fluxes and fluid dynamics data are provided by the VSOP code. Capabilities of the FRESCO-I and SPATRA code which allow for the simulation of the redistribution of fission products within the primary circuit and the deposition of fission products on graphitic and metallic surfaces are also available in STACY. In this paper, details of the STACY model and first results for its application to the 200 MW(th) HTR
International Nuclear Information System (INIS)
RETAIN-S is a code for calculating fission product transport in a multicompartment system. The fission products can occur in the form of aerosols and vapours, and revaporization due to surface heating is taken into consideration. The aerosol model uses log-normal approximation for size distribution. The differences between RETAIN-S and the Industry Degraded Core Rulemaking (IDCOR) version of RETAIN are mentioned briefly. The method for calculating condensation of vapours and vaporization due to heating is described. The results of test calculations made on the Surry AB sequence defined by the Group of Experts on the Source Term (GREST) are given and compared with corresponding NAUA results. It is concluded that the degree of agreement is strongly dependent on the model used for gravitational agglomeration efficiency. The calculations made on a Marviken-V experiment are also reported. It is shown that the results are dependent on the possible condensation of fission product vapour on the walls and on aerosols. In addition, the results are given for a BWR meltdown sequence characterized by a large loss-of-coolant accident with loss of all AC power. One important conclusion is that the source term after containment break is mainly determined by the possible re-evaporation of fission products. (author)
International Nuclear Information System (INIS)
This work, on electron pair production, is in three parts. Measure of energetic and angular distributions for baryum and uranium at 1.33 MeV. The results on the baryum are in good agreement with the exact calculations and show that the influence of screening effects is important on uranium. The measure was made with a streamer chamber associated with magnetic field and stereoscopic taking of photographs. Analytic continuation of electron pair production to the tip of the positon spectrum in point-Coulomb calculation. At high energy the value of this point is not zero. Determination of a set of parameters in order to input the exact cross sections in electron gamma showers calculation above 5 MeV for lead
Takamiya, K; Imanaka, T; Egbert, S D; Rühm, W
2011-05-01
In a previous paper, Takamiya et al. calculated (63)Ni production in copper samples exposed to the Hiroshima atomic bomb. More specifically, they used their experimental cross-section values of the (63)Cu(n,p)(63)Ni reaction and compared the result with that of the corresponding calculation in the radiation dosimetry system DS02, which used another set of cross-section values. These results were different, and the following two reasons were found: typographical errors in several energy boundary values in the DS02 report that was also used in the calculation by Takamiya et al. and an inappropriate assumption on the cross-section values of the low neutron energy region in the calculation by Takamiya et al. These two issues are described and amended in the present report. PMID:21327808
Production of negative ions on graphite surface in H2/D2 plasmas: Experiments and srim calculations
International Nuclear Information System (INIS)
In previous works, surface-produced negative-ion distribution-functions have been measured in H2 and D2 plasmas using graphite surfaces (highly oriented pyrolitic graphite). In the present paper, we use the srim software to interpret the measured negative-ion distribution-functions. For this purpose, the distribution-functions of backscattered and sputtered atoms arising due to the impact of hydrogen ions on a-CH and a-CD surfaces are calculated. The srim calculations confirm the experimental deduction that backscattering and sputtering are the mechanisms of the origin of the creation of negative ions at the surface. It is shown that the srim calculations compare well with the experiments regarding the maximum energy of the negative ions and reproduce the experimentally observed isotopic effect. A discrepancy between calculations and measurements is found concerning the yields for backscattering and sputtering. An explanation is proposed based on a study of the emitted-particle angular-distributions as calculated by srim.
2013-05-31
... of the 2003 tax rates because those tax rates have changed (75 FR 76921, December 10, 2010). USDA has... HUMAN SERVICES Food and Drug Administration 21 CFR Part 1150 RIN 0910-AG81 Tobacco Products, User Fees... of Tobacco Products AGENCY: Food and Drug Administration, HHS. ACTION: Proposed rule. SUMMARY:...
Directory of Open Access Journals (Sweden)
Mihai BERCA
2013-01-01
Full Text Available The Pedoclimatic Index (PCI calculated by us is the product between the Aridity Index (AR and the soil fertility status expressed through number of creditworthiness points (CWS – Creditworthiness of Soil: PCI = AR x CWS .Was used AR calculated after UNEP (United Nations Environment Programme instead of the older De Martonne index. Determinations were performed in 6 different pedoclimatic areas, in which PCI has varied from 12 to 47. Taking into account that AR varies between 0,20 and 1,00 in Romania, while CWS is between 0 and 100, theoretically PCI can range in the interval 0-100 and practically from 10 to 50. For each PCI was calculated the wheat production according to the Technological Processes Intensity (TPI, Creditworthiness (CWS, them also with marks from 1 to 10, and the wheat production pattern was made based on the two parameters. It appears that at a very reduced and reduced index of the technological processes (TPI between 1-4 the wheat yields level is very slightly influenced by the pedoclimatic quality of the culture area. In the areals of culture with PCI below 15 the production can’t reach 30 q/ha, irrespective of the quality of technological processes. At PCI of over 40 the production achieves 60 q/ha if there are applied superior technologies and if the working capital is optimum used. At PCI between 30 and 40 the maximum yield that can be reached in conditions of highest technical and qualitative value of production slightly exceeds 50 q/ha. All these models and nomograms are useful to agricultural management in order to estimate the production, but also for her optimization
International Nuclear Information System (INIS)
Measurements of neutron pulse time-width and intensity have been carried out on grids of small moderators placed side by side and decoupled by cadmium strips; a moderator concept introduced by the authors through previous publications. Transport calculations are based on the standard reactor code DOT 3.5 with the ENDF-B IV nuclear data library. (orig.)
Energy Technology Data Exchange (ETDEWEB)
Lee, C.E.; Apperson, C.E. Jr.; Foley, J.E.
1976-10-01
The report describes an analytic containment building model that is used for calculating the leakage into the environment of each isotope of an arbitrary radioactive decay chain. The model accounts for the source, the buildup, the decay, the cleanup, and the leakage of isotopes that are gas-borne inside the containment building.
International Nuclear Information System (INIS)
The report describes an analytic containment building model that is used for calculating the leakage into the environment of each isotope of an arbitrary radioactive decay chain. The model accounts for the source, the buildup, the decay, the cleanup, and the leakage of isotopes that are gas-borne inside the containment building
Energy Technology Data Exchange (ETDEWEB)
Wemhoener, C.; Afjei, Th
2003-07-01
This final report for the Swiss Federal Office of Energy (SFOE) presents the results of work done at the University of Applied Sciences Basel, in Muttenz, Switzerland, on the development of a simple method of calculating the seasonal performance of residential heat pumps that are used to simultaneously provide heat for both space heating and hot water preparation. The report reviews the 'state of the art' concerning calculation methods and existing standards and discusses the shortcomings of some of these methods as a basis for the further development. The principles of the method proposed are explained and the calculation steps involved are described. Sources for base-data for the individual calculation steps are described, such as meteorological data, heat-source temperature, heating and hot water demand and the coefficient of performance of the heat pumps used. Also, heat losses due to cyclic operation, test procedures and factors for simultaneous operation are discussed, whereby both theoretical values and results from simulations are presented. Finally, the method is applied to two sample systems.
Espinosa-Garcia, Joaquin; Corchado, Jose C
2016-03-01
For the OH + CH4/CD4 hydrogen abstraction reactions, the methyl radical (CH3 and CD3) product translational distributions and the water (H2O and HOD) product vibrational distributions experimentally reported by Liu's group are reproduced by quasi-classical trajectory (QCT) calculations on an analytical full-dimensional potential energy surface when a quantum spirit is included in the analysis. Our simulations correctly predict: (i) the vibrational excitation of the water product, (ii) the inversion of the water vibrational population, and (iii) the propensity of transfer from reactant kinetic energy to product translational energy. These reactions therefore present a marked isotopic effect. In addition, the water product vibrational distributions for the OH/OD + CH4 reactions agree reasonably well with Butkovskaya and Setser's experiments for a similar alkane reaction. The theory/experiment agreement is better for the HOD than for the H2O product due to the mode coupling in the H2O molecule, which is absent in the HOD stretching modes, which show a more "local" character. In summary, for polyatomic systems with many degrees of freedom (15 in the present reaction), QCT calculations analyzed with a quantum spirit represent a useful alternative to quantum scattering methods. PMID:26061483
International Nuclear Information System (INIS)
For the OECD/NEA code intercomparison, nuclide production cross sections of 16O, 27Al, natFe, 59Co, natZr and 197Au for the proton incidence with energies of 20 MeV to 5 GeV are calculated with the HETC-3STEP code based on the intranuclear cascade evaporation model including the preequilibrium and high energy fission processes. In the code, the level density parameter derived by Ignatyuk, the atomic mass table of Audi and Wapstra and the mass formula derived by Tachibana et al. are newly employed in the evaporation calculation part. The calculated results are compared with the experimental ones. It is confirmed that HETC-3STEP reproduces the production of the nuclides having the mass number close to that of the target nucleus with an accuracy of a factor of two to three at incident proton energies above 100 MeV for natZr and 197Au. However, the HETC-3STEP code has poor accuracy on the nuclide production at low incident energies and the light nuclide production through the fragmentation process induced by protons with energies above hundreds of MeV. Therefore, further improvement is required. (author)
International Nuclear Information System (INIS)
A calculational technique for quantifying the concentration of hydrogen generated by radiolysis in sealed radioactive waste containers was developed in a U.S. Department of Energy (DOE) study conducted by EG ampersand G Idaho, Inc., and the Electric Power Research Institute (EPRI) TMI-2 Technology Transfer Office. The study resulted in report GEND-041, entitled open-quotes A Calculational Technique to Predict Combustible Gas Generation in Sealed Radioactive Waste Containersclose quotes. The study also resulted in a presentation to the U.S. Nuclear Regulatory Commission (NRC) which gained acceptance of the methodology for use in ensuring compliance with NRC IE Information Notice No. 84-72 (NRC 1984) concerning the generation of hydrogen within packages. NRC IE Information Notice No. 84-72: open-quotes Clarification of Conditions for Waste Shipments Subject to Hydrogen Gas Generationclose quotes applies to any package containing water and/or organic substances that could radiolytically generate combustible gases. EPRI developed a simple computer program in a spreadsheet format utilizing GEND-041 calculational methodology to predict hydrogen gas concentrations in low-level radioactive wastes containers termed Radcalc. The computer code was extensively benchmarked against TMI-2 (Three Mile Island) EPICOR II resin bed measurements. The benchmarking showed that the model developed predicted hydrogen gas concentrations within 20% of the measured concentrations. Radcalc for Windows was developed using the same calculational methodology. The code is written in Microsoft Visual C++ 2.0 and includes a Microsoft Windows compatible menu-driven front end. In addition to hydrogen gas concentration calculations, Radcalc for Windows also provides transportation and packaging information such as pressure buildup, total activity, decay heat, fissile activity, TRU activity, and transportation classifications
International Nuclear Information System (INIS)
Radiotoxicity is one of important characteristics of radwaste hazard. Radiotoxicity of actinides and fission products from spent fuel of VVER-1000 reactor for processes of burnup, long-term storage, and transmutation is discussed. (author)
Hörtenhuber, Stefan; Lindenthal, Thomas; Amon, Barbara; Markurt, Theresia; Kirner, Leopold; Zollitsch, Werner
2010-01-01
The aim of this study was to analyze various Austrian dairy production systems (PS) concerning their greenhouse gas emissions (GHGE) in a life-cycle chain, including effects of land-use change (LUC). Models of eight PS that differ, on the one hand, in their regional location (alpine, uplands and lowlands) and, on the other hand, in their production method (conventional versus organic, including traditional and recently emerging pasture-based dairy farming) were designed. In general, the GH...
Argento, D.; Reedy, R. C.; Stone, J. O.
2012-12-01
Cosmogenic nuclides have been used to develop a set of tools critical to the quantification of a wide range of geomorphic and climatic processes and events (Dunai 2010). Having reliable absolute measurement methods has had great impact on research constraining ice age extents as well as providing important climatic data via well constrained erosion rates, etc. Continuing to improve CN methods is critical for these sciences. While significant progress has been made in the last two decades to reduce uncertainties (Dunai 2010; Gosse & Phillips 2001), numerous aspects still need to be refined in order to achieve the analytic resolution desired by glaciologists and geomorphologists. In order to investigate the finer details of the radiation responsible for cosmogenic nuclide production, we have developed a physics based model which models the radiation cascade of primary and secondary cosmic-rays through the atmosphere. In this study, a Monte Carlo method radiation transport code, MCNPX, is used to model the galactic cosmic-ray (GCR) radiation impinging on the upper atmosphere. Beginning with a spectrum of high energy protons and alpha particles at the top of the atmosphere, the code tracks the primary and resulting secondary particles through a model of the Earth's atmosphere and into the lithosphere. Folding the neutron and proton flux results with energy dependent cross sections for nuclide production provides production rates for key cosmogenic nuclides (Argento et al. 2012, in press; Reedy 2012, in press). Our initial study for high latitude shows that nuclides scale at different rates for each nuclide (Argento 2012, in press). Furthermore, the attenuation length for each of these nuclide production rates increases with altitude, and again, they increase at different rates. This has the consequence of changing the production rate ratio as a function of altitude. The earth's geomagnetic field differentially filters low energy cosmic-rays by deflecting them away
International Nuclear Information System (INIS)
The solubility of the transmutants and construction materials can influence the corrosion of the target vessel and the circuit components. In addition the solubility has an influence on the formation of solid depositions on the surfaces as well as on the segregation of mobile solid particles. As a first step calculations of the partial molar enthalpies of mixing at in infinite dilution were performed using the Miedema-Model. The bonding energies of metallic elements with mercury are present as periodic function in dependence on the atomic number. In a second step an extension was performed with the introduction of the latent enthalpies and entropies of transformation and fusion of the metallic elements. In case of formation of amalgams the integral molar formation enthalpies of the mercury-richest intermetallic compounds were considered. The calculated partial molar enthalpies of solution are discussed in comparison with literature data. For metals which co-exist in pure state with the saturated solution in liquid mercury the solubilities were calculated in the temperature range between 400 - 550 K. (author)
International Nuclear Information System (INIS)
Purified Cyanex 301 which contains >99% bis(2,4,4-trimethylpentyl)dithio-phosphinic acid (HBTMPDTP) shows high extraction selectivity toward Am3+ over light lanthanides (Lns). In a bench scale 4 stage cross-flow hot test, 99.999% of Am in Am+Lns fraction obtained from a hot experiment of the TRPO extraction of a real HAW was extracted while only 3% Lns was co-extracted. The average separation factor of Am over FPLns is about 3500. An empirical distribution ratio model for Am and Lns in HBTMPDTP extraction and a method of countercurrent extraction process parameter calculation were established and the results of calculation were verified with tracer amount of 241Am and macro amount of Lns. For an Am+Lns fraction with typical PWR HAW composition, the calculated results show that a five stage countercurrent HBTMPDTP extraction process without scrubbing can get a separation of Am from Lns of 106 and a separation of Lns from Am of 700. (author)
Lazarev, V.; Geidmanis, D.
2016-02-01
The theoretical problem solved in this article is the calculation of thermodynamic parameters such as final temperature, distribution of the liquid and dry saturated vapour phases of the substance that are considered to be in thermodynamic equilibrium, and pressure of the system of several reaction products after adding to the system a certain amount of heat or the thermal effect released during rapid exothermic reaction in a closed volume that occurs so fast that it can be considered to be adiabatic, and when the volume of liquid reagents is several orders of magnitude less than the volume of the reactor. The general multi-substance problem is reduced to a theoretical problem for one substance of calculation thermodynamic parameters of system after adding a certain amount of heat that gives theoretically rigorous isochoric calculation. In this article, we substantiate our view that isochoric pass of calculation is more robust compared to seemingly more natural isobaric pass of calculation, if the later involves quite not trivial calculation of the adiabatic compression of a two-phase system (liquid - dry saturated vapour) that can pass itself into another kind of state (liquid - wet saturated vapour), which requires, apparently, more complex descriptions compared with isochoric calculation because the specific heat capacity of wet saturated vapour can be negative. The solved theoretical problem relates to a practical problem that has been a driver for our research as part of a design of the reactor of the titanium reduction from magnesium and titanium tetrachloride supplied into atmosphere of the reactor at high temperatures when both reagents are in gaseous state. The reaction is known to be exothermic with a high thermal effect, and estimate of the final temperature and pressure of the products of reaction, for instance, designing the reactor allows eliminating the possibility of the reaction products to penetrate backwards into supply tracts of the reagents
Hong, S W; Lee, D H; Ryu, C Y
1999-01-01
Calculations of the LAMBDA-hypernucleus production cross section in the (pi sup + ,K sup +) reaction are presented. The nuclear reaction part is treated within the distorted wave impulse approximation, and the nuclear structure part is based on the Green function formalism. In the nuclear reaction part, the pion and Kaon distorted wave functions and the elementary transition amplitudes for N(pi,K)GAMMA are properly employed to construct an external field. The formalism allows us to calculate the wave function of LAMBDA's in nuclei by taking care of both bound and continuum states of the LAMBDA. The quasi-free peak, as well as bound state peaks, are reproduced by the calculation. The LAMBDA knock-out and spreading mode are separated and compared with the coincidence measurement data.
Czech Academy of Sciences Publication Activity Database
Buděšínský, Miloš; Vaněk, Václav; Dračínský, Martin; Pohl, Radek; Poštová Slavětínská, Lenka; Sychrovský, Vladimír; Pícha, Jan; Císařová, I.
2014-01-01
Roč. 70, č. 25 (2014), s. 3871-3886. ISSN 0040-4020 R&D Projects: GA ČR GA203/09/1919; GA ČR GA13-24880S Institutional support: RVO:61388963 Keywords : six-membered saturated heterocycles (N, P, S, Se) * oxidation products * configuration * NMR * quantum chemical calculations * X-ray structures Subject RIV: CC - Organic Chemistry Impact factor: 2.641, year: 2014
Gadomski, P. J.; Deems, J. S.; Glennie, C. L.; Hartzell, P. J.; Butler, H.; Finnegan, D. C.
2015-12-01
The use of high-resolution topographic data in the form of three-dimensional point clouds obtained from laser scanning systems (LiDAR) is becoming common across scientific disciplines.However little consideration has typically been given to the accuracy and the precision of LiDAR-derived measurements at the individual point scale.Numerous disparate sources contribute to the aggregate precision of each point measurement, including uncertainties in the range measurement, measurement of the attitude and position of the LiDAR collection platform, uncertainties associated with the interaction between the laser pulse and the target surface, and more.We have implemented open-source software tools to calculate per-point stochastic measurement errors for a point cloud using the general LiDAR georeferencing equation.We demonstrate the use of these propagated uncertainties by applying our methods to data collected by the Airborne Snow Observatory ALS, a NASA JPL project using a combination of airborne hyperspectral and LiDAR data to estimate snow-water equivalent distributions over full river basins.We present basin-scale snow depth maps with associated uncertainties, and demonstrate the propagation of those uncertainties to snow volume and snow-water equivalent calculations.
International Nuclear Information System (INIS)
Wave propagational inverse problems arise in several applications including medical imaging and geophysical exploration. In these problems, one is interested in obtaining the parameters describing the medium from its response to excitations. The problems are characterized by their large size, and by the hyperbolic equation which models the physical phenomena. The inverse problems are often posed as a nonlinear data-fitting where the unknown parameters are found by minimizing the misfit between the predicted data and the actual data. In order to solve the problem numerically using a gradient-type approach, one must calculate the action of the Jacobian and its adjoint on a given vector. In this paper, the authors explore the use of automatic differentiation (AD) to develop codes that perform these calculations. They show that by exploiting structure at 2 scales, they can arrive at a very efficient code whose main components are produced by AD. In the first scale they exploit the time-stepping nature of the hyperbolic solver by using the Extended Jacobian framework. In the second (finer) scale, they exploit the finite difference stencil in order to make explicit use of the sparsity in the dependence of the output variables to the input variables. The main ideas in this work are illustrated with a simpler, one-dimensional version of the problem. Numerical results are given for both one- and two-dimensional problems. They present computational templates that can be used in conjunction with optimization packages to solve the inverse problem
Energy Technology Data Exchange (ETDEWEB)
NONE
2002-05-01
After having analyzed the answers given to the public inquiry about the methods used for the calculation of the saved costs, the French commission of electricity regulation (CRE) indicates in this document the trends it has retained for the calculation of the charges of the power production public utility for 2002: cost overruns due to the obligation of purchase and to the purchase contracts anterior to the law from February 10, 2000; production cost overruns in non-interconnected areas (Corsica and overseas departments). (J.S.)
International Nuclear Information System (INIS)
A mass transfer coefficient (kla) and an axial effective diffusivity (De) of U in the separation of U from fission products using ion exchange method have been calculated. In this separation process, mass transfer of uranium occurs in the liquid and solid phases. Mathematical model calculation is started by setting up mass balances on an element volume in the ion exchange column which can be assumed to have a similarity to the above process. The set up differential equations (in the form of simultaneous differential equations) are then solved using numerical analysis method. It is started by predicting the (kla) value to obtain the uranium concentrations as a function of distance and time, CA1(x,t) and XA1(x,t). Both the resulted concentrations of uranium and the predicted kla are used to calculate De and concentrations of uranium in the liquid, CA2(x,t) and solid phases, XA2(x,t). The resulted concentrations of uranium are then compared with the concentrations of uranium in the previous calculation. Both the kla and De values can be accepted if the difference between the concentrations resulted from both the calculations are similar or nearly equal, i.e the concentration difference performed by sum of squares of errors (SSE) is minimum (nearly zero). For the superficial linear velocity of about 20-40 cm/minute the results from the calculations are kl a= 15.18588 -20. 48588 per minute and De = 9.14117x10-4 - 1.11612x10-3 cm2/minute. The sum of squares of errors and the average relative error on the condition above are about 2.25117.10-9 - 3.98145x10-9 and 11,541% -25.981%
International Nuclear Information System (INIS)
We present the results of a complete tree-level calculation of the processes pp(anti p)→Wb anti b and Wb anti b+jet that includes the single-top signal and all irreducible backgrounds simultaneously. In order to probe the structure of the Wtb coupling with the highest possible accuracy and to look for possible deviations from standard model predictions, we identify sensitive observables and propose an optimal set of cuts which minimizes the background, as compared to the signal. At the Large Hadron Collider (LHC), the single-top and the single-antitop rates are different, and the corresponding asymmetry yields additional information. The analysis shows that the sensitivity for anomalous couplings will be improved at the LHC by a factor of 2-3, as compared to the expectations for the first measurements at the upgraded Tevatron. Still, the bounds on anomalous couplings obtained at hadron colliders will remain 2-8 times larger than those from high-energy γe colliders; however, these will not be available for some time. All basic calculations have been carried out using the computer package CompHEP. The known next-to-leading-order corrections to the single-top rate have been taken into account. (orig.)
Directory of Open Access Journals (Sweden)
M. D. Corre
2010-03-01
Full Text Available Soil respiration is the second largest flux in the global carbon cycle, yet the underlying belowground process, carbon dioxide (CO2 production, is not well understood because it can not be measured in the field. CO2 production has frequently been calculated from the vertical CO2 diffusive flux divergence, known as "soil-CO2 profile method". This relatively simple method requires knowledge of soil CO2 concentration profiles and soil diffusive properties. Application of the method in a tropical lowland forest soil in Panama gave inconsistent results when using diffusion coefficients (D calculated based on relationships with soil porosity and moisture (empirical D. Our objective was to investigate whether these inconsistencies were caused by (1 the applied interpolation and solution methods, (2 uncertainties in describing the profile of D using empirical equations, or (3 the assumptions of the soil-CO2 profile method. We show that the calculated CO2 production strongly depended on the function used to interpolate between measured CO2 concentrations. With an inverse analysis of the soil-CO2 profile method we deduce which D would be required to explain the observed CO2 concentrations, assuming the model assumptions are valid. In the top soil, this inverse D closely resembled the empirical D. In the deep soil, however, the inverse D increased sharply while the empirical D did not. This deviation between the empirical and inverse D disappeared upon conducting a constrained fit parameter optimization. A radon (Rn mass balance model, in which diffusion was calculated based on the empirical or constrained inverse D, simulated the observed Rn profiles reasonably well. However, the CO2 concentrations which corresponded to the constrained inverse D were too small compared to the measurements, and the inverse D gave depth-constant fluxes and hence zero production in the soil CO2-profile method. We suggest that, in well-structured soils, a missing description
International Nuclear Information System (INIS)
The Monte Carlo design of the waste assay region of a dual assay system, to be installed at the Fluorinal and Storage Facility, is described. The instrument will be used by the facility operator to assay high-enriched spent fuel packages and waste solids produced from dissolution of the fuels. The fissile content discharged in the waste is expected to vary between 0 and 400 g of 235U. Material accountability measurements of the waste must be obtained in the presence of large neutron (0.5 x 106 n/s) and gamma (50,000 R/hr) backgrounds. The assay system employs fast-neutron irradiation of the sample, using a 5 mg 252Cf source, followed by delayed neutron counting after the source is transferred to storage. Calculations indicate a +-4-g (2 sigma) assay for a waste canister containing 300 g of 235U is achievable with an end-of-life (1 mg) 252Cf source and a background rate of 0.5 x 106 n/s
Feng, Ping; Baugh, Steve
2013-01-01
A method for the calculation of the whey protein fraction was developed for milk-based infant formula products based upon amino acid ratio calculated from asparaginelaspartic acid, alanine, proline, and phenylalanine amino acid data. Historical and literature amino acid data were combined to establish the reference amino acid values used in the validation study. This method has been evaluated for accuracy versus label claim for 12 products, with results from 90 to 107.5% of label claim and an overall average of 98.7%. Repeatability and intermediate precision were determined over 4 different days. Repeatability results were 4.75, 2.06, 4.18, and 2.44% RSD, respectively, with an overall intermediate precision of 3.68% RSD. Since the amino acid profile of infant formula finished products depends on the amino acid profile of ingredients used, the applicability of the method needs to be confirmed for specific types of infant formula, for which data will be gathered. Additional reference material data are being gathered for better estimation of milk and whey reference values, which are based on being normalized to total amino acid content, during the two year AOAC INTERNATIONAL Official Methods of Analysis method approval process. PMID:24000754
Energy Technology Data Exchange (ETDEWEB)
Mueller, Don E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Marshall, William J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wagner, John C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bowen, Douglas G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2015-09-01
The U.S. Nuclear Regulatory Commission (NRC) Division of Spent Fuel Storage and Transportation recently issued Interim Staff Guidance (ISG) 8, Revision 3. This ISG provides guidance for burnup credit (BUC) analyses supporting transport and storage of PWR pressurized water reactor (PWR) fuel in casks. Revision 3 includes guidance for addressing validation of criticality (k_{eff}) calculations crediting the presence of a limited set of fission products and minor actinides (FP&MA). Based on previous work documented in NUREG/CR-7109, recommendation 4 of ISG-8, Rev. 3, includes a recommendation to use 1.5 or 3% of the FP&MA worth to conservatively cover the bias due to the specified FP&MAs. This bias is supplementary to the bias and bias uncertainty resulting from validation of k_{eff} calculations for the major actinides in SNF and does not address extension to actinides and fission products beyond those identified herein. The work described in this report involves comparison of FP&MA worths calculated using SCALE and MCNP with ENDF/B-V, -VI, and -VII based nuclear data and supports use of the 1.5% FP&MA worth bias when either SCALE or MCNP codes are used for criticality calculations, provided the other conditions of the recommendation 4 are met. The method used in this report may also be applied to demonstrate the applicability of the 1.5% FP&MA worth bias to other codes using ENDF/B V, VI or VII based nuclear data. The method involves use of the applicant s computational method to generate FP&MA worths for a reference SNF cask model using specified spent fuel compositions. The applicant s FP&MA worths are then compared to reference values provided in this report. The applicants FP&MA worths should not exceed the reference results by more than 1.5% of the reference FP&MA worths.
International Nuclear Information System (INIS)
As part of the Initial Feasibility Study of the Fast Mixed Spectrum Reactor, a series of benchmark calculations were made to determine the sensitivity of the physics analysis to differences in methods and data. Argonne National Laboratory (ANL), the Massachusetts Institute of Technology (MIT), and Oak Ridge National Laboratory (ORNL) were invited to participate with Brookhaven National Laboratory in the analysis of a FMSR model prescribed by BNL. Detailed comparisons are made including a comprehensive study on the adequacy of the fission product treatments
Directory of Open Access Journals (Sweden)
M. D. Corre
2010-08-01
Full Text Available Soil respiration is the second largest flux in the global carbon cycle, yet the underlying below-ground process, carbon dioxide (CO2 production, is not well understood because it can not be measured in the field. CO2 production has frequently been calculated from the vertical CO2 diffusive flux divergence, known as "soil-CO2 profile method". This relatively simple model requires knowledge of soil CO2 concentration profiles and soil diffusive properties. Application of the method for a tropical lowland forest soil in Panama gave inconsistent results when using diffusion coefficients (D calculated based on relationships with soil porosity and moisture ("physically modeled" D. Our objective was to investigate whether these inconsistencies were related to (1 the applied interpolation and solution methods and/or (2 uncertainties in the physically modeled profile of D. First, we show that the calculated CO2 production strongly depends on the function used to interpolate between measured CO2 concentrations. Secondly, using an inverse analysis of the soil-CO2 profile method, we deduce which D would be required to explain the observed CO2 concentrations, assuming the model perception is valid. In the top soil, this inversely modeled D closely resembled the physically modeled D. In the deep soil, however, the inversely modeled D increased sharply while the physically modeled D did not. When imposing a constraint during the fit parameter optimization, a solution could be found where this deviation between the physically and inversely modeled D disappeared. A radon (Rn mass balance model, in which diffusion was calculated based on the physically modeled or constrained inversely modeled D, simulated observed Rn profiles reasonably well. However, the CO2 concentrations which corresponded to the constrained inversely modeled D were too small compared to the measurements. We suggest that, in well-structured soils, a missing description of steady state CO2
Doubleday, Charles; Boguslav, Mayla; Howell, Caronae; Korotkin, Scott D; Shaked, David
2016-06-22
An unusual H/D kinetic isotope effect (KIE) is described, in which isotopic selectivity arises primarily from nonstatistical dynamics in the product. In DFT-based quasiclassical trajectories of Bergman cyclization of (Z)-3-hexen-1,5-diyne (1) at 470 K, the new CC bond retains its energy, and 28% of nascent p-benzyne recrosses back to the enediyne on a vibrational time scale. The competing process of intramolecular vibrational redistribution (IVR) in p-benzyne is too slow to prevent this. Deuteration increases the rate of IVR, which decreases the fraction of recrossing and increases the yield of statistical (trapable) p-benzyne, 2. Trapable yields for three isotopomers of 2 range from 72% to 86%. The resulting KIEs for Bergman cyclization differ substantially from KIEs predicted by transition state theory, which suggests that IVR in this reaction can be studied by conventional KIEs. Leakage of vibrational zero point energy (ZPE) into the reaction coordinate was probed by trajectories in which initial ZPE in the CH/CD stretching modes was reduced by 25%. This did not change the predicted KIEs. PMID:27281683
Velinov, P. I. Y.; Mateev, L. N.
2008-02-01
The effects of galactic cosmic rays (CRs) in the middle atmosphere are considered in this work. We take into account the CR modulation by solar wind and the anomalous CR component also. In fact, CRs determine the electric conductivity in the middle atmosphere and influence the electric processes in itin this way. CRs introduce solar variability in the terrestrial atmosphere and ozonosphere--because they are modulated by solar wind. A new analytical approach for CR ionization by protons and nuclei with charge Z in the lower ionosphere is developed in this paper. For this purpose, the ionization losses (dE/dh) according to the Bohr-Bethe-Bloch formula for the energetic charged particles are approximated in three different energy intervals. More accurate expressions for CR energy decrease E(h) and electron production rate profiles q(h) are derived. The obtained formulas allow comparatively easy computer programming. q(h) is determined by the solution of a 3D integral with account of geomagnetic cut-off rigidity. The integrand in q(h) gives the possibility for application of adequate numerical methods--in this case Gauss quadrature, for the solution of the mathematical problem. Computations for CR ionization in the middle atmosphere are made. In this way the process of interaction of CR particles with the upper and middle atmosphere are described much more realistically. The full CR composition is taken into account: protons, helium ([alpha]-particles), light L, medium M, heavy H and very heavy VH group of nuclei. All computations are made for geomagnetic cut-off rigidity R=1 GV in the altitude interval 15-120 km. The COSPAR International Reference Atmosphere CIRA'86 is applied in the computer program for the neutral density and scale height values. The proposed improved CR ionization model will contribute to the quantitative understanding of solar-atmosphere relationships.
International Nuclear Information System (INIS)
We investigate the initial and secondary oxidation products on the Si(111)-(7 × 7) surface at room-temperature using atomic force microscopy (AFM) and density functional theory calculations. At the initial oxidation stages, we find that there are two types of bright spots in AFM images. One of them is identified as a Si adatom with one O atom inserted into one of the backbonds, while the other is ascribed to a Si adatom with two inserted O atoms. We observe that the latter one turns into the secondary oxidation product by a further coming O2 molecule, which appears as a more protruded bright spot. The atomic configuration of this product is identified as Si adatom whose top and all three backbonds make bonds with O atoms. The appearances of initial and secondary oxidation products are imaged as bright and dark sites by scanning tunneling microscopy, respectively. It is revealed that AFM gives us the topographic information close to the real atomic corrugation of adsorbed structures on the semiconductor surfaces
International Nuclear Information System (INIS)
The inventory estimation of long-lived fission products (LLFP) is essential for the long-term safety assessment of a geological disposal of high-level radioactive waste (HLW). 79Se and 135Cs are a main contributor to the total dose from the geological repository of HLW, owing to their solubility in the strata. In this study, the post-irradiation experimental data of LLFPs, such as 79Se, 99Tc, 126Sn and 135Cs, were compared with ORIGEN2 calculation using the data library of JENDL-3.3. A fragment of the UO2 fuel pellet irradiated in a commercial Japanese PWR was dissolved with nitric acid in a hot cell. The resultant solution was filtered to remove insoluble residue. After Se, Tc, Sn, and Cs were chemically separated, the concentrations of 79Se, 99Tc, 126Sn and 135Cs were determined with an inductively coupled plasma quadruple mass spectrometer (ICP-QMS). The concentration of 79Se, 99Tc, 126Sn and 135Cs in the sample solution were 0.78±0.22, 101±24, 3.2±0.6, and 68±6.0 ng/g of the sample solution (ng/g-sol), respectively. The results for 79Se and 135Cs obtained in this study showed good agreement with those obtained through ORIGEN2 calculation. This indicates that ORIGEN2 calculation is applicable to the estimation of the amounts of 79Se and 135Cs generated during irradiation. In contrast, the experimentally determined concentration of 99Tc and 126Sn were equivalent to approximately 70% and 60%, respectively, of those obtained through ORIGEN2 calculation. (author)
Energy Technology Data Exchange (ETDEWEB)
Perez, Daniel Milian; Lorenzo, Daniel E. Milian; Garcia, Lorena P. Rodriguez; Llanes, Jesus Salomon; Hernandez, Carlos R. Garcia, E-mail: dperez@instec.cu, E-mail: dmilian@instec.cu, E-mail: lorenapilar@instec.cu, E-mail: cgh@instec.cu [Instituto Superior de Tecnologias y Ciencias Aplicadas (InSTEC), La Habana (Cuba); Lira, Carlos A. Brayner de Oliveira, E-mail: cabol@ufpe.br [Universidade Federal de Pernambuco (UFPE), Recife (Brazil); Rodriguez, Manuel Cadavid, E-mail: mcadavid2001@yahoo.com [Tecnologia Nuclear Medica Spa, TNM (Chile)
2015-07-01
{sup 99m}Tc is the most common radioisotope used in nuclear medicine. It is a very useful radioisotope, which is used in about 30-40 million procedures worldwide every year. Medical diagnostic imaging techniques using {sup 99m}Tc represent approximately 80% of all nuclear medicine procedures. Although {sup 99m}Tc can be produced directly on a cyclotron or other type of particle accelerator, currently is almost exclusively produced from the beta-decay of its 66-h parent {sup 99}Mo. {sup 99}Mo production system in an Aqueous Homogeneous Reactor (AHR) is potentially advantageous because of its low cost, small critical mass, inherent passive safety, and simplified fuel handling, processing and purification characteristics. In this paper, an AHR conceptual design using Low Enriched Uranium (LEU) is studied and optimized for the production of {sup 99}Mo. Aspects related with the neutronic behavior such as optimal reflector thickness, critical height, medical isotopes production and the reactivity feedback introduced in the solution by the volumetric expansion of the fuel solution due to thermal expansion of the fuel solution and the void volume generated by radiolytic gas bubbles were evaluated. Thermal-hydraulics studies were carried out in order to show that sufficient cooling capacity exists to prevent fuel overheating. The neutronic and thermal-hydraulics calculations have been performed with the MCNPX computational code and the version 14 of ANSYS CFX respectively. The neutronic calculations demonstrated that the reactor is able to produce 370 six-day curies of {sup 99}Mo in 5 days operation cycles and the CFD simulation demonstrated that the heat removal systems provide sufficient cooling capacity to prevent fuel overheating, the maximum temperature reached by the fuel (89.29 deg C) was smaller to the allowable temperature limit (90 deg C). (author)
International Nuclear Information System (INIS)
Extensive studies on the transfer of radiocaesium from soil to agricultural products under long term field conditions have been performed in Sweden since 1961. Effects of various remedial measures to be taken after farm land contamination have been studied in long term microplot experiments, in ploughing experiments and in conventional field experiments in Chernobyl fallout areas. Furthermore, the transfer of radiocaesium in various farm ecosystems, as influenced by farm management practices and the line of production applied, has been calculated. Fertilization with potassium has been found to effectively reduce the transfer of radiocaesium from the soil to various crops. The best effects were found on peat and sandy soils in the Chernobyl fallout areas, where a reduction by a factor of 2-5 or more has been recorded. Also, on clay soils heavy K application was found to depress the Cs transfer appreciably. Placement of the nuclide below the normal ploughing depth reduced the Cs transfer by a factor of 2-3 as compared with the effect of a homogeneous distribution in the plough layer. With a combination of deep placement and K fertilization a reduction by a factor of 10 or more has been obtained. It seems possible to reduce the caesium transfer from soil to food by a factor of 5-10 by changing the line of production on a farm in various ways. (author). 12 refs, 5 tabs
车间生产精益驾驶舱数显参量设计与计算%Numerical parameter design and calculation of lean production dashboard
Institute of Scientific and Technical Information of China (English)
王志国; 唐任仲
2009-01-01
基于车间生产精益驾驶舱的管理思想,设计了精益驾驶舱仪表盘.在分析仪表盘设计参量指标内容和选取原则的基础上,构建仪表盘参量指标体系.结合工位信息模型、车间工位级实时数据采集以及现场生产管理仪表盘参量指标体系,分析从可采集的车间生产现场数据到生产系统运作参数设计过程,提出驾驶舱参量指标的计算模型--"数据-参量转换公式组".以某玩具机器人装配生产过程为例开展了实例研究,从而验证了指标体系结构的合理性和计算模型的有效性.%A lean visual dashboard was designed based on the management theory of lean production dashboard (LPD). The parameter index system of the visual dashboard was established on the basis of analyzing the content and selection principle of the dashboard's parameter index. Combined with the workstation information model and the real-time data acquisition of parameter index system of the dashboard, a calculation model of LPD parameter index was developed through studying the processes from collecting data to displaying parameter. The method was applied to the assembly production of toy robots. Results show that the parameter index system of LPD is reasonable and the calculation model is feasible.
Bonnet, L; Corchado, J
2015-01-01
Ten years ago, Liu and co-workers measured pair-correlated product speed and angular distributions for the OH+CH4/CD4 reactions at the collision energy of ~ 10 kcal/mol [B. Zhang, W. Shiu, J. J. Lin and K. Liu, J. Chem. Phys 122, 131102 (2005); B. Zhang, W. Shiu and K. Liu, J. Phys. Chem. A 2005, 109, 8989]. Recently, two of us could semi-quantitatively reproduce these measurements by performing full-dimensional classical trajectory calculations in a quantum spirit on an ab-initio potential energy surface of their own [J. Espinosa-Garcia and J. C. Corchado, Theor Chem Acc, 2015, 134, 6 ; J. Phys. Chem. B, Article ASAP, DOI: 10.1021/acs.jpcb.5b04290]. The goal of the present work is to show that these calculations can be significantly improved by adding a few more constraints to better comply with the experimental conditions. Overall, the level of agreement between theory and experiment is remarkable considering the large dimensionality of the processes under scrutiny.
Harlander, Robert V.; Liebler, Stefan; Mantler, Hendrik
2013-06-01
This article describes the code SusHi (for "Supersymmetric Higgs") [108] which calculates the cross sections pp/pp ¯ →ϕ+X in gluon fusion and bottom-quark annihilation in the SM and the MSSM, where ϕ is any of the neutral Higgs bosons within these models. Apart from inclusive cross sections up to NNLO QCD, differential cross sections with respect to the Higgs transverse momentum pT and (pseudo-)rapidity y(η) can be calculated through NLO QCD. In the case of gluon fusion, SusHi contains NLO QCD contributions from the third family of quarks and squarks, NNLO corrections due to top-quarks, approximate NNLO corrections due to top-squarks, and electro-weak effects. It supports various renormalization schemes for the sbottom sector and the bottom Yukawa coupling, as well as resummation effects of higher order tanβ-enhanced sbottom contributions. SusHi provides a link to FeynHiggs for the calculation of the Higgs masses. Program SummaryProgram title: SusHi Catalogue identifier: AEOY_v1_0 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/AEOY_v1_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 47725 No. of bytes in distributed program, including test data, etc.: 338380 Distribution format: tar.gz Programming language: Fortran 77. Computer: Personal computer. Operating system: Unix/Linux, Mac OS. RAM: A few 100 MB Classification: 11.1. External routines: LHAPDF (http://lhapdf.hepforge.org), FeynHiggs (http://www.feynhiggs.de) Nature of problem: Calculation of inclusive and exclusive Higgs production cross sections in gluon fusion and bottom-quark annihilation in the Standard Model and the MSSM through next-to-leading order QCD, includes next-to-next-to-leading order top-(s)quark contributions and electro-weak effects Solution method: Numerical Monte Carlo integration
Calculation of Greenhouse Gases Emission from Agricultural Production in China%中国农业生产温室气体排放量的测算
Institute of Scientific and Technical Information of China (English)
闵继胜; 胡浩
2012-01-01
As China is a large agricultural country, and China' s greenhouse gases of agricultural production occupy a great proportion in the total greenhouse gases emission, it is very important to calculate greenhouse gases from the agricultural production process in China. In light of the previous research and various greenhouse gases emission factors of crop and livestock, this study aimed at preliminarily calculating the greenhouse gases emission from agricultural production in China during 1991 -2008. We found that: (1) Methane emission of crop decreased from 9 995 000 t in 1991 to 9 314 400 t in 2008, but nitrous oxide emission of crop increased from 346 700 t in 1991 to 487 400 t in 2008. (2) Methane and nitrous oxide emission of livestock showed a trend of "inverse U-shape" : Methane emission increased from 7 635 300 t in 1991 to 11 114 300 t in 2006 and then decreased to 9 007 400 t in 2008. Nitrous oxide emission increased from 353 200 t in 1991 to 559 300 t in 2006 and then decreased to 469 000 t in 2008. (3) On the regional angle, greenhouse gases emission from agricultural production in Sichuan (plus Chongqing City) , Hunan, Jiangsu, Henan, Shandong and Anhui Provinces are in the front ranks of greenhouse gases emission of agricultural production in China.%农业生产的温室气体排放在总排放量中占有较大比重,中国是农业大国,因此,对中国农业生产的温室气体排放量进行测算显得尤为重要.借鉴前人研究,结合农业生产中各种产品的温室气体排放系数,对1991 -2008年中国农业生产的温室气体排放量进行了初步测算.结果表明:①1991-2008年,种植业的CH4排放量从999.5万t下降到931.44万t,N2O的排放量从34.67万t增加到48.74万t;②同期间的畜牧业的CH4和N2O排放量均星先升后降的趋势；CH4排放量从1991年的763.53万t上升到2006年的1111.43万t后,又下降到2008年的900.74万t;N2O排放量从1991年的35.32万t上升到2006年的55.93
SRD 166 MEMS Calculator (Web, free access) This MEMS Calculator determines the following thin film properties from data taken with an optical interferometer or comparable instrument: a) residual strain from fixed-fixed beams, b) strain gradient from cantilevers, c) step heights or thicknesses from step-height test structures, and d) in-plane lengths or deflections. Then, residual stress and stress gradient calculations can be made after an optical vibrometer or comparable instrument is used to obtain Young's modulus from resonating cantilevers or fixed-fixed beams. In addition, wafer bond strength is determined from micro-chevron test structures using a material test machine.
Indian Academy of Sciences (India)
R Baldik; H Aytekin; E Tel
2013-02-01
In this study, the pre-equilibrium and equilibrium calculations of cross-sections of 89Y(, ), 90Zr$(p, xn)$ and 94Mo(, ) reactions, which were used for the production of 89Zr, 90Nb and 94Tc positron-emitting radioisotopes, have been investigated. Pre-equilibrium calculations have been performed at different proton incident energies by using the hybrid, geometry-dependent-hybrid and full exciton models. The Weisskopf–Ewing model is used for calculating the equilibrium effects at the same incident energies. The calculated results have been discussed and compared with the experimental results.
Directory of Open Access Journals (Sweden)
Kaluđerović-Radoičić Tatjana
2015-01-01
Full Text Available In this paper the process of the copper (II sulphate monohydrate from copper (II sulphate pentahydrate (also known as a Blue vitriol or Bluestone production was analyzed. Copper (II sulphate pentahydrate is one of the most important copper salts which has been known since the ancient Egyptians. In the nineteenth century its application as a fungicide was discovered which provoked wide industrial production. Molecule of the copper (II sulphate pentahydrate is a crystalohydrate with five water molecules linked by chemical bonds to a molecule of the copper (II sulphate. Copper (II sulphate exists as a series of compounds that differ in their degree of hydratation. The anhydrous form is a pale green or gray-white powder, whereas the pentahydrate (CuSO4•5H2O, the most commonly encountered salt, is bright blue. In order to obtain copper (II sulphate monohydrate from copper (II sulphate pentahydrate four water molecules need to be removed. To determine the optimum temperature and time required for the removal of four water molecules from a molecule of pentahydrate in this work thermogravimetric (TGA analysis was performed. Thermogravimetric (TGA analysis - dehydration of copper (II sulphate pentahydrate is done using simultaneous TG-DSC thermal analyzer DTG-Q600 SDT from TA Instruments. Analyzes was carried out for two type of samples, the sample containing particles of the average diameter equal to 0.17 mm and the particles of the average diameter 0.5 mm. In addition, fluidization and drying curve was determined using a semi-industrial fluidization column. On top, the industrial fluidization column aimed to produce 300 tones per month of copper (II sulphate monohydrate was designed. Material and energy calculations were performed using software packages Simprosys 3.0 and SuperPro Designer 5.1. Simprosys 3.0 is a software package designed for the modeling and simulation of a drying process as well as for 20 different unit operations. Super
DEFF Research Database (Denmark)
Petersen, Kurt Erling
1986-01-01
probabilistic approaches have been introduced in some cases for the calculation of the reliability of structures or components. A new computer program has been developed based upon numerical integration in several variables. In systems reliability Monte Carlo simulation programs are used especially in analysis...... of very complex systems. In order to increase the applicability of the programs variance reduction techniques can be applied to speed up the calculation process. Variance reduction techniques have been studied and procedures for implementation of importance sampling are suggested....
Shielding calculations for SSC
International Nuclear Information System (INIS)
Monte Carlo calculations of hadron and muon shielding for SSC are reviewed with emphasis on their application to radiation safety and environmental protection. Models and algorithms for simulation of hadronic and electromagnetic showers, and for production and transport of muons in the TeV regime are briefly discussed. Capabilities and limitations of these calculations are described and illustrated with a few examples. 12 refs., 3 figs
Annual energy production calculation in wind farm based on physical model%风电场发电量计算的物理模型
Institute of Scientific and Technical Information of China (English)
王丹; 孙昶辉
2011-01-01
风电场发电量是定量评估拟建风电场效益的重要指标,特别在地形复杂区域,现有风电场发电量计算方法不能较好地反映实际情况.为此,通过对风电场发电量影响因素的分析,引入了物理模型即粗糙度模型和地形模型,考虑了风电场的局部效应对风电场风能资源的影响,采用解析原理分析风电场局地效应与风电机组尾流影响,较为精确地模拟了拟建风电场的风能资源,从而提高风电场的效益.%Annual Energy Production (AEP) is an important index in quantitative benefit evaluation of planned wind farm. The real situation cannot be reflected by existing AEP calculation methods accurately, especially in complex terrain area. Influencing factors of AEP in wind farm were analyzed; physical models such as roughness model and terrain model were introduced. With the consideration of wind electrical field local effort influence on the wind resources, an analytic method was proposed to analyze the local effect of wind farm and wake effect of wind turbines. The proposed method can provide accurate simulation of wind resources in planned wind farm, which can in turn better evaluate the benefits in the planning stage.
International Nuclear Information System (INIS)
At this study, isotopic evolution of the sample E58-263 of assembly WZR0058 of Vandellos Unit II (PWR-Spain) is calculated with MONTEBURNS code system. The sample was exposed with different neutron spectrum because of its different core location at fuel different cycles. At fuel calculation, all fuel cycle burn-up history of Use sample is 1 considered consecutively by using the 'remove' and 'add' option of the MONTEBURNS code. The calculated results are compared with fuel measurement and with cycle by cycle calculation methodology results.
Beguería, Santiago; Vicente Serrano, Sergio M.
2009-01-01
[EN] *Objectives: The program calculates time series of the Standardised Precipitation-Evapotransporation Index (SPEI). *Technical Characteristics: The program is executed from the Windows console. From an input data file containing monthly time series of precipitation and mean temperature, plus the geographic coordinates of the observatory, the program computes the SPEI accumulated at the time interval specified by the user, and generates a new data file with the SPEI time serie...
International Nuclear Information System (INIS)
Reviewed is the effect of heat flux of different system parameters on critical density in order to give an initial view on the value of several parameters. A thorough analysis of different equations is carried out to calculate burnout is steam-water flows in uniformly heated tubes, annular, and rectangular channels and rod bundles. Effect of heat flux density distribution and flux twisting on burnout and storage determination according to burnout are commended
International Nuclear Information System (INIS)
for evaluation of homolog chemical properties. CAMS also offers an environment for testing these systems 'online' by incorporating automated chemical systems into the beamline so that tracers can be created, transported, and chemically separated all on the shorter timescales required for transactinide experiments. Even though CAMS is limited in the types and energies of ions they can accelerate, there are still a wide variety of reactions that can be performed there with commercially available target materials. The half-lives of these isotopes vary over a range that could be used for both online chemistry (where shorter half-lives are required) and benchtop tracers studies (where longer lived isotopes are preferred). In this document, they present a summary of tracer production reactions that could be performed at CAMS, specifically for online, automated chemical studies. They are from chemical groups four through seven, 13, and 14, which would be appropriate for studies of elements 104-107, 113, and 114. Reactions were selected that had (a) commercially available target material, (b) half-lives long enough for transport from a target chamber to an automated chemistry system, and (c) cross-sections at CAMS available projectile energies that were large enough to produce enough atoms to result in a statistically relevant signal after losses for transport and chemistry were considered. In addition, the resulting product atoms had to decay with an observable gamma-ray using standard Ge gamma-ray detectors. The table includes calculations performed for both metal targets and their corresponding oxides.
Energy Technology Data Exchange (ETDEWEB)
Moody, K J; Shaughnessy, D A; Gostic, J M
2011-11-29
for evaluation of homolog chemical properties. CAMS also offers an environment for testing these systems 'online' by incorporating automated chemical systems into the beamline so that tracers can be created, transported, and chemically separated all on the shorter timescales required for transactinide experiments. Even though CAMS is limited in the types and energies of ions they can accelerate, there are still a wide variety of reactions that can be performed there with commercially available target materials. The half-lives of these isotopes vary over a range that could be used for both online chemistry (where shorter half-lives are required) and benchtop tracers studies (where longer lived isotopes are preferred). In this document, they present a summary of tracer production reactions that could be performed at CAMS, specifically for online, automated chemical studies. They are from chemical groups four through seven, 13, and 14, which would be appropriate for studies of elements 104-107, 113, and 114. Reactions were selected that had (a) commercially available target material, (b) half-lives long enough for transport from a target chamber to an automated chemistry system, and (c) cross-sections at CAMS available projectile energies that were large enough to produce enough atoms to result in a statistically relevant signal after losses for transport and chemistry were considered. In addition, the resulting product atoms had to decay with an observable gamma-ray using standard Ge gamma-ray detectors. The table includes calculations performed for both metal targets and their corresponding oxides.
McCarty, George
1982-01-01
How THIS BOOK DIFFERS This book is about the calculus. What distinguishes it, however, from other books is that it uses the pocket calculator to illustrate the theory. A computation that requires hours of labor when done by hand with tables is quite inappropriate as an example or exercise in a beginning calculus course. But that same computation can become a delicate illustration of the theory when the student does it in seconds on his calculator. t Furthermore, the student's own personal involvement and easy accomplishment give hi~ reassurance and en couragement. The machine is like a microscope, and its magnification is a hundred millionfold. We shall be interested in limits, and no stage of numerical approximation proves anything about the limit. However, the derivative of fex) = 67.SgX, for instance, acquires real meaning when a student first appreciates its values as numbers, as limits of 10 100 1000 t A quick example is 1.1 , 1.01 , 1.001 , •••• Another example is t = 0.1, 0.01, in the functio...
International Nuclear Information System (INIS)
Risk and reliability analysis is increasingly being used in evaluations of plant safety and plant reliability. The analysis can be performed either during the design process or during the operation time, with the purpose to improve the safety or the reliability. Due to plant complexity and safety and availability requirements, sophisticated tools, which are flexible and efficient, are needed. Such tools have been developed in the last 20 years and they have to be continuously refined to meet the growing requirements. Two different areas of application were analysed. In structural reliability probabilistic approaches have been introduced in some cases for the calculation of the reliability of structures or components. A new computer program has been developed based upon numerical integration in several variables. In systems reliability Monte Carlo simulation programs are used especially in analysis of very complex systems. In order to increase the applicability of the programs variance reduction techniques can be applied to speed up the calculation process. Variance reduction techniques have been studied and procedures for implementation of importance sampling are suggested. (author)
Derrickson, J. H.; Dake, S.; Dong, B. L.; Eby, P. B.; Fountain, W. F.; Fuki, M.; Gregory, J. C.; Hayashi, T.; Iyono, A.; King, D. T.
1989-01-01
Recently, new calculations were made of the direct Coulomb pair cross section that rely less in arbitrary parameters. More accurate calculations of the cross section down to low pair energies were made. New measurements of the total direct electron pair yield, and the energy and angular distribution of the electron pairs in emulsion were made for O-16 at 60 and 200 GeV/amu at S-32 at 200 GeV/amu which give satisfactory agreement with the new calculations. These calculations and measurements are presented along with previous accelerator measurements made of this effect during the last 40 years. The microscope scanning criteria used to identify the direct electron pairs is described. Prospects for application of the pair method to cosmic ray energy measurements in the region 10 (exp 13) to 10 (exp 15) eV/amu are discussed.
International Nuclear Information System (INIS)
Cross-sections for the production of de-excitation γ rays following inelastic neutron scattering have been calculated, using the statistical model, and are given for natural chromium and nickel for neutron incident energy up to 10MeV
International Nuclear Information System (INIS)
The future CERN collider (LHC) has a fantastic potential of discovery, provided quantum chromodynamics can be quantitatively predicted. To do so, it is necessary to work at NLO approximation in order to reduce the dependence of the -cross-section on- the non-physical scales. To obtain results in this approximation, one has to calculate the cross-sections of the partonic subprocesses contributing to the studied reaction at the lowest order, and also the virtual corrections (loop corrections) and the real corrections. The calculation of the virtual corrections remains very complicated if the number of external particles is greater than four or if the external (internal) particles are massive. in this thesis, an automatic method which enables to calculate one loop diagrams with five external legs and which can be generalized to the case of massive particles is presented. In a first part, we describe different tools and methods necessary to such calculations. We then apply -them to the calculation of the gg →γγ g reaction, which interests the ATLAS and CMS experimentalists as the background for the Higgs boson search. We also give the explicit result for this amplitude for each helicity configuration in a compact form and a clearly gauge invariant representation. We finally present a phenomenological study of this reaction. (author)
Harlander, Robert V.; Liebler, Stefan; Mantler, Hendrik(TH Division, Physics Department, CERN, CH-1211, Geneva 23, Switzerland)
2012-01-01
This article describes the code SusHi (for "Supersymmetric Higgs") which calculates the cross sections $pp/p\\bar{p}\\rightarrow\\phi+X$ in gluon fusion and bottom-quark annihilation in the SM and the MSSM, where $\\phi$ is any of the neutral Higgs bosons within these models. Apart from inclusive cross sections up to NNLO QCD, differential cross sections with respect to the Higgs' transverse momentum $p_T$ and (pseudo-)rapidity $y(\\eta)$ can be calculated through NLO QCD. In case of gluon fusion,...
Sampaio, J. M.; Guerra, M.; Parente, F.; Madeira, T. I.; Indelicato, P.; Santos, J. P.; Marques, J. P.
2016-09-01
In this paper, we calculate the K-, L- and M-shells X-ray production, and X-ray fluorescence cross-sections after photo-induced ionization, for Zn, Cd, and Hg, and for incident photon energy range from 1 to 150 keV. For this purpose, the corresponding average fluorescence yields for Zn, Cd, and Hg as well as the photoionization cross-sections were calculated using the Dirac-Fock method. Subshell fluorescence, intrashell and intershell yields are obtained consistently from radiative and radiationless transitions calculated in the exact same method. A comprehensive account of the relations between the X-ray production, X-ray fluorescence cross-sections and the photoionization cross-sections and these yields is presented. Comparisons are made with results from other authors. The obtained values for the photoionization cross-sections are in good agreement with the widely used data of Scofield in the studied energy range. However our results for the X-ray fluorescence cross sections seem to favor some data relatively to others. The energy dependence of the average fluorescence yields is discussed, in particular, the reliability of extrapolated data for lighter elements from measurements and calculations in heavier elements above the inner shell absorption edges is questioned. Tabulated data on photoionization and X-ray production cross-sections are presented for the incident photon energy range 1-150 keV in steps of 1 keV.
Djouadi, Abdelhak
2002-01-01
I discuss the various available tools for the study of the properties of the new particles predicted in the Minimal Supersymmetric extension of the Standard Model. Emphasis will be put on the codes for the determination of the sparticle and Higgs boson spectrum. Codes for the calculation of production cross sections, decay widths and branching ratios, Dark Matter relic density and detection rates, as well as codes for automatic analytical calculations and Monte-Carlo event generators for Supersymmetric processes will be briefly discussed.
Czech Academy of Sciences Publication Activity Database
Buděšínský, Miloš; Vaněk, Václav; Dračínský, Martin; Pohl, Radek; Poštová Slavětínská, Lenka; Sychrovský, Vladimír; Pícha, Jan; Císařová, I.
Hersonissos: -, 2013. s. 612-612. [EUROMAR 2013. A European Magnetic Resonance Meeting. 30.06.2013-05.07.2013, Hersonissos] R&D Projects: GA ČR GA13-24880S Institutional support: RVO:61388963 Keywords : NMR * 1H * 13C * six-membered saturated heterocycles * oxidation * DFT and HF calculations Subject RIV: CB - Analytical Chemistry, Separation
Aspects of yield and specific activity of (n,γ) produced 177Lu used in targeted radionuclide therapy
International Nuclear Information System (INIS)
177Lu-labeled receptor avid peptides and monoclonal antibodies have been effectively used in targeted tumor therapy, owing to the ideally suited decay properties and favourable production logistics of 177Lu [T½ = 6.65 days; Eβ(max) = 497 keV (78.6 %); Eγ = 208 keV (11.0 %)]. The specific activity of 177Lu produced by the (n,γ) route is one of the important criteria, which determines the efficacy of 177Lu-labeled receptor-avid biomolecules. The present article highlights that the specific activity of (n,γ) produced 177Lu cannot be calculated by simply dividing the produced activity by the mass of the target irradiated, unlike other (n,γ) produced medical radioisotopes and there is a significant enhancement of specific activity due to the burn up of the Lu target during irradiation, which is an added advantage towards the utilization of 177Lu in receptor specific therapeutic radiopharmaceuticals. (author)
International Nuclear Information System (INIS)
The temperature regime is calculated for two different designs of containers with uranium-bearing material for the upgraded VVR-Ts research reactor facility (IVV.10M). The containers are to be used in the production of 99Mo. It is demonstrated that the modification of the container design leads to a considerable temperature reduction and an increase in the near-wall boiling margin and allows one to raise the amount of material loaded into the container. The calculations were conducted using the international thermohydraulic contour code TRAC intended to analyze the technical safety of water-cooled nuclear power units
Energy Technology Data Exchange (ETDEWEB)
Kazantsev, A. A., E-mail: kazantsevanatoly@gmail.com [Experimental Scientific Research and Methodology Center Simulation Systems (Russian Federation); Sergeev, V. V. [Leipunsky Institute of Physics and Power Engineering (Russian Federation); Kochnov, O. Yu. [Karpov Institute of Physical Chemistry (Obninsk Branch) (Russian Federation)
2015-12-15
The temperature regime is calculated for two different designs of containers with uranium-bearing material for the upgraded VVR-Ts research reactor facility (IVV.10M). The containers are to be used in the production of {sup 99}Mo. It is demonstrated that the modification of the container design leads to a considerable temperature reduction and an increase in the near-wall boiling margin and allows one to raise the amount of material loaded into the container. The calculations were conducted using the international thermohydraulic contour code TRAC intended to analyze the technical safety of water-cooled nuclear power units.
Kazantsev, A. A.; Sergeev, V. V.; Kochnov, O. Yu.
2015-12-01
The temperature regime is calculated for two different designs of containers with uranium-bearing material for the upgraded VVR-Ts research reactor facility (IVV.10M). The containers are to be used in the production of 99Mo. It is demonstrated that the modification of the container design leads to a considerable temperature reduction and an increase in the near-wall boiling margin and allows one to raise the amount of material loaded into the container. The calculations were conducted using the international thermohydraulic contour code TRAC intended to analyze the technical safety of water-cooled nuclear power units.
Indian Academy of Sciences (India)
François Arleo; Pol-Bernard Gossiaux; Thierry Gousset; Jörg Aichelin
2003-04-01
For more than 25 years /Ψ production has helped to sharpen our understanding of QCD. In proton induced reaction some observations are rather well understood while others are still unclear. The current status of the theory of /Ψ production will be sketched, paying special attention to the issues of formation time and /Ψ re-interaction in a nuclear medium.
Directory of Open Access Journals (Sweden)
Papp P.
2008-01-01
Full Text Available A theoretical treatment is used to perform conformational studies of title compounds, which was previously successfully used within our group for characterization of fragmentation patterns of some bio-molecules. Now we present studies of electron impact ionization of 2 Furanmethanol, Tetrahydro (C5H10O2 and 3-Furanol, Tetrahydro (C4H8O2, both as important models for more complicated compounds like nucleic acids. In this paper geometry of the neutral and cationic conformers of these two molecules was optimized on the DFT level with B3LYP functional, and ionization energies were estimated. DFT calculated results are supplemented with G3MP2 calculations, and a set of higher-level ab initio methods were empirically corrected to obtain more reliable results.
Czech Academy of Sciences Publication Activity Database
Onoda, J.; Ondráček, Martin; Yurtsever, A.; Jelínek, Pavel; Sugimoto, Y.
2014-01-01
Roč. 104, č. 13 (2014), "133107-1"-"133107-4". ISSN 0003-6951 R&D Projects: GA ČR(CZ) GA14-02079S Grant ostatní: AVČR(CZ) M100101207 Institutional support: RVO:68378271 Keywords : silicon surface * oxidation * atomic force microscopy * scanning tunneling microscopy * first principles calculations Subject RIV: BM - Solid Matter Physics ; Magnetism Impact factor: 3.302, year: 2014
Harlander, Robert V; Mantler, Hendrik
2012-01-01
This article describes the code SusHi (for "Supersymmetric Higgs") which calculates the cross sections $pp/p\\bar{p}\\rightarrow\\phi+X$ in gluon fusion and bottom-quark annihilation in the SM and the MSSM, where $\\phi$ is any of the neutral Higgs bosons within these models. Apart from inclusive cross sections up to NNLO QCD, differential cross sections with respect to the Higgs' transverse momentum $p_T$ and (pseudo-)rapidity $y(\\eta)$ can be calculated through NLO QCD. In case of gluon fusion, SusHi contains NLO QCD contributions from the third family of quarks and squarks, NNLO corrections due to top-quarks, approximate NNLO corrections due to top-squarks, and electro-weak effects. It supports various renormalization schemes for the sbottom sector and the bottom Yukawa coupling, as well as resummation effects of higher order $\\tan\\beta$-enhanced sbottom contributions. SusHi provides a link to FeynHiggs for the calculation of the Higgs masses.
Gail, Matthias; Grün, Norbert; Scheid, Werner
2003-04-01
Coupled channel calculations are performed for electron-positron pair production in relativistic collisions of heavy ions. For this purpose the wavefunction is expanded into different types of basis sets consisting of atomic wavefunctions centred around the projectile ion only and around both of the colliding nuclei. The results are compared with experimental data from Belkacem et al (1997 Phys. Rev. A 56 2807). This work is part of the doctoral thesis of Matthias Gail, Giessen (D26) 2001.
CELSS scenario analysis: Breakeven calculations
Mason, R. M.
1980-01-01
A model of the relative mass requirements of food production components in a controlled ecological life support system (CELSS) based on regenerative concepts is described. Included are a discussion of model scope, structure, and example calculations. Computer programs for cultivar and breakeven calculations are also included.
International Nuclear Information System (INIS)
ORIGEN-S computes time-dependent concentrations and source terms of a large number of isotopes, which are simultaneously generated or depleted through neutronic transmutation, fission, radioactive decay, input feed rates and physical or chemical removal rates. The calculations may pertain to fuel irradiation within nuclear reactors, or the storage, management, transportation or subsequent chemical processing of removed fuel elements. The matrix exponential expansion model of the ORIGEN code is unaltered in ORIGEN-S. Essentially all features of ORIGEN were retained, expanded or supplemented within new computations. The primary objective of ORIGEN-S, as requested by the Nuclear Regulatory Commission, is that the calculations may utilize the multi-energy-group cross sections from any currently processed standardized ENDF/B data base. This purpose has been implemented through the prior execution of codes within either the SCALE System or the AMPX System, developed at the Oak Ridge National Laboratory. These codes compute flux-weighted cross sections, simulating conditions within any given reactor fuel assembly, and convert the data into a library that can be input to ORIGEN-S. Time-dependent libraries may be produced, reflecting fuel composition variations during irradiation. Presented in the document are: detailed and condensed input instructions, model theory, features available, range of applicability, brief subroutine descriptions, sample input, and I/O requirements
International Nuclear Information System (INIS)
Fission-product and actinide decay heating, gas content, curies, and detailed contributions of the most important nuclide contributors were supplied in a series of letters following requests from the Presidential Commission on the Accident at Three Mile Island. In addition, similar data assuming different irradiation (power) histories were requested for purposes of comparison. This report consolidates the tabular and graphical data supplied and explains its basis
International Nuclear Information System (INIS)
Fission-product and actinide decay heating, gas content, curies, and detailed contributions of the most important nuclide contributors were supplied in a series of letters following requests from the Presidential Commission on the Accident at Three Mile Island. In addition, similar data assuming different irradiation (power) histories were requested for purposes of comparison. This report consolidates the tabular and graphical data supplied and explains its basis
Energy Technology Data Exchange (ETDEWEB)
England, T.R.; Wilson, W.B.
1979-10-01
Fission-product and actinide decay heating, gas content, curies, and detailed contributions of the most important nuclide contributors were supplied in a series of letters following requests from the Presidential Commission on the Accident at Three Mile Island. In addition, similar data assuming different irradiation (power) histories were requested for purposes of comparison. This report consolidates the tabular and graphical data supplied and explains its basis.
France, J. L.; King, M. D.; Lee-Taylor, J.; Beine, H. J.; Ianniello, A.; Domine, F.; MacArthur, A.
2011-12-01
Depth-integrated production rates of OH radicals and NO2 molecules from snowpacks in Ny-Ålesund, Svalbard, are calculated from fieldwork investigating the light penetration depth (e-folding depth) and nadir reflectivity of snowpacks during the unusually warm spring of 2006. Light penetration depths of 8.1, 11.3, 5.1, and 8.2 cm were measured for fresh, old, marine-influenced, and glacial snowpacks, respectively (wavelength 400 nm). Radiative-transfer calculations of the light penetration depths with reflectivity measurements produced scattering cross sections of 5.3, 9.5, 20, and 25.5 m2 kg-1 and absorption cross sections of 7.7, 1.4, 3.4, and 0.5 cm2 kg-1 for the fresh, old, marine-influenced, and glacial snowpacks, respectively (wavelength 400 nm). Photolysis rate coefficients, J, are presented as a function of snow depth and solar zenith angle for the four snowpacks for the photolysis of H2O2 and NO3-. Depth-integrated production rates of hydroxyl radicals are 1270, 2130, 950, and 1850 nmol m-2 h-1 (solar zenith angle of 60°) for fresh, old, marine-influenced, and glacial snowpacks, respectively. Depth-integrated production rates of NO2 are 32, 56, 11, and 22 nmol m-2 h-1 (solar zenith angle of 60°) for the fresh, old, marine-influenced, and glacial snowpacks, respectively. The uncertainty of repeated light penetration depth measurement was determined to be ˜20%, which propagates into a 20% error in depth-integrated production rates. A very simple steady state hydroxyl radical calculation demonstrates that a pseudo first-order loss rate of OH radicals of ˜102-104 s-1 is required in snowpack. The snowpacks around Ny-Ålesund are thick enough to be considered optically infinite.
Hansen, Kenneth; Altwegg, Kathrin; Berthelier, Jean-Jacques; Bieler, Andre; Calmonte, Ursina; Combi, Michael; De Keyser, Johan; Fiethe, Björn; Fougere, Nicolas; Fuselier, Stephen; Gombosi, Tamas; Hässig, Myrtha; Huang, Zhenguang; Le Roy, Lena; Rubin, Martin; Tenishev, Valeriy; Toth, Gabor; Tzou, Chia-Yu
2016-04-01
We have previously used results from the AMPS DSMC (Adaptive Mesh Particle Simulator Direct Simulation Monte Carlo) model to create an empirical model of the near comet coma (coma model to significantly further from the comet (~100,000-1,000,000 km). The empirical model characterizes the neutral coma in a comet centered, sun fixed reference frame as a function of heliocentric distance, radial distance from the comet, local time and declination. Furthermore, we have generalized the model beyond application to 67P by replacing the heliocentric distance parameterizations and mapping them to production rates. Using this method, the model become significantly more general and can be applied to any comet. The model is a significant improvement over simpler empirical models, such as the Haser model. For 67P, the DSMC results are, of course, a more accurate representation of the coma at any given time, but the advantage of a mean state, empirical model is the ease and speed of use. One application of the empirical model is to de-trend the spacecraft motion from the ROSINA COPS and DFMS data (Rosetta Orbiter Spectrometer for Ion and Neutral Analysis, Comet Pressure Sensor, Double Focusing Mass Spectrometer). The ROSINA instrument measures the neutral coma density at a single point and the measured value is influenced by the location of the spacecraft relative to the comet and the comet-sun line. Using the empirical coma model we can correct for the position of the spacecraft and compute a total production rate based on the single point measurement. In this presentation we will present the coma production rate as a function of heliocentric distance both pre- and post-equinox and perihelion.
Field, J. H.
1994-03-01
A new event generator for lepton pair production and wide angle Bhabha scattering, BHAGENE3, is presented. Both electroweak and higher order (beyond O(α) QED corrections are included. Comparisons are made with results from the programs, based on the structure function formalism, ALIBABA, TOPAZ0 and ZFITTER. For the case of the final states l+l-γγ ( l = e, μ, τ) BHAGENE3 results are compared with those of Monte Carlo generators that use the exact O( α2) amplitudes.
Energy Technology Data Exchange (ETDEWEB)
Rovny, Sergey I.; Mokrov, Y.; Stukalov, Pavel M.; Beregich, D. A.; Teplyakov, I. I.; Anspaugh, L. R.; Napier, Bruce A.
2009-10-23
The Mayak Production Association (MPA) was established in the late 1940s in accordance with a special Decree of the USSR Government for the production of nuclear weapons. In early years of MPA operation, due to the lack of experience and absence of effective methods of RW management, the enterprise had extensive routine (designed) and non-routine (accidental) releases of gaseous radioactive wastes to the atmosphere. These practices resulted in additional technogenic radiation exposure of residents inhabiting populated areas near the MPA. The primary objective of ongoing studies under JCCRER Project 1.4 is to estimate doses to the residents of Ozersk due to releases of radioactive substances from the stacks of MPA. Preliminary scoping studies have demonstrated that releases of radioactive iodine (131I) from the stacks of the Mayak Radiochemical Plant represented the major contribution to the dose to residents of Ozersk and of other nearby populated areas. The behavior of 131I in the environment and of 131I migration through biological food chains (vegetation-cows-milk-humans) indicated a need for use of special mathematical models to perform the estimation of radiation doses to the population. The goal of this work is to select an appropriate model of the iodine migration in biological food chains and to justify numerical values of the model parameters.
International Nuclear Information System (INIS)
The Mayak Production Association (MPA) was established in the late 1940s in accordance with a special Decree of the USSR Government for the production of nuclear weapons. In early years of MPA operation, due to the lack of experience and absence of effective methods of RW management, the enterprise had extensive routine (designed) and non-routine (accidental) releases of gaseous radioactive wastes to the atmosphere. These practices resulted in additional technogenic radiation exposure of residents inhabiting populated areas near the MPA. The primary objective of ongoing studies under JCCRER Project 1.4 is to estimate doses to the residents of Ozersk due to releases of radioactive substances from the stacks of MPA. Preliminary scoping studies have demonstrated that releases of radioactive iodine (131I) from the stacks of the Mayak Radiochemical Plant represented the major contribution to the dose to residents of Ozersk and of other nearby populated areas. The behavior of 131I in the environment and of 131I migration through biological food chains (vegetation-cows-milk-humans) indicated a need for use of special mathematical models to perform the estimation of radiation doses to the population. The goal of this work is to select an appropriate model of the iodine migration in biological food chains and to justify numerical values of the model parameters.
Directory of Open Access Journals (Sweden)
Firman Menne
2013-07-01
Full Text Available Economic conditions should be viewed as the catalyst for developing the ability to intelligently manage resources so that the people of Indonesia can be out of the condition. Effective management and efficiency is reflected in good planning and good planning requires good information. In order to plan well the utilization of company resources to fold the duplicate spiders, company management requires system information revealed by clearly and precisely the facts relating to the activity. PT Semen Tonasa is a fabrication company doing business in the field of cement industry and produces two types of cement, cement or Portland cement type 1 can (OPC and Portland cement (PPC Pazzolan. The benefits that can be gained if the company implemented the system of Activity-Based Costing are: elimination is obtained more accurate information, among others, to improve the quality of decision making. In the ABC product only burdened costs of resources and activities that are used and does not burdened by the cost of the resources and activities. This method causes the cost per unit of a more stable and consistent with the purposes of the imposition of costs to the product result in activity.
On Calculation of Amplitudes in Quantum Electrodynamics
Karplyuk, Kostyantyn; Zhmudsky, Oleksandr
2012-01-01
A new method of calculation of amplitudes of different processes in quantum electrodynamics is proposed. The method does not use the Feynman technique of trace of product of matrices calculation. The method strongly simplifies calculation of cross sections for different processes. The effectiveness of the method is shown on the cross-section calculation of Coulomb scattering, Compton scattering and electron-positron annihilation.
International Nuclear Information System (INIS)
Systems loaded with plutonium in the form of mixed-oxide (MOX) fuel show somewhat different neutronic characteristics compared with those using conventional uranium fuels. In order to maintain adequate safety standards, it is essential to accurately predict the characteristics of MOX-fuelled systems and to further validate both the nuclear data and the computation methods used. A computation benchmark on power distribution within fuel assemblies to compare different techniques used in production codes for fine flux prediction in systems partially loaded with MOX fuel was carried out at an international level. It addressed first the numerical schemes for pin power reconstruction, then investigated the global performance including cross-section data reduction methods. This report provides the detailed results of this second phase of the benchmark. The analysis of the results revealed that basic data still need to be improved, primarily for higher plutonium isotopes and minor actinides. (author)
Institute of Scientific and Technical Information of China (English)
贾兴真; 银燕; 张聿为
2012-01-01
目的利用Excel数据表格形式对消毒产品试验数据的计算与检验进行简化与格式化，以提高工作效率、减少出现人为错误。方法在Excel表格中设定、输入相应的格式和函数公式，通过其自动程序对数据进行计算、检验。结果只需在Excel中直接输入试验所获数据就可快速准确地计算出试验结果，并对试验数据是否符合相应要求给出判断结论。结论在消毒产品试验数据的计算与检验中使用Excel可以大大提高计算的速度与准确性，具有实际应用价值。%Objective To simplify and format the calculating and verifying the test data of disinfection product, and to improve work efficiency and decrease human error, the excel sheet is used. Methods Input proper functions into the excel sheet and set corresponding formation, through its auto program to calculate and verify the data. Results The results are rapidly and accurately worked out and the conclusion if the data is agreed with corresponding requirements is gotten only if input the test data into the excel sheet. Conclusion The calculating speed and accuracy is improved dramatically by using excel to calculate and verify the test data of disinfection product. It has practical value.
Energy Technology Data Exchange (ETDEWEB)
Demir, Bayram [Istanbul Univ. (Turkey). Physics Dept.; Kaplan, A.; Capali, V. [Univ. Isparta (Turkey). Physics Dept.; Sarpuen, I.H. [Afyon Kocatepe Univ., Afyonkarahisar (Turkey). Physics Dept.; Aydin, A. [Kirikkale Univ. (Turkey). Physics Dept.; Tel, E. [Univ. Osmaniye (Turkey). Physics Dept.
2015-03-15
In this study, production cross-section calculations of {sup 32}P, {sup 117}Sn, {sup 153}Sm and {sup 186,188}Re radionuclides used in bone pain palliation treatment produced by {sup 30}Si(d,γ){sup 32}P, {sup 118}Sn(γ,n){sup 117}Sn, {sup 116}Sn(n,γ){sup 117}Sn, {sup 150}Nd(α,n){sup 153}Sm, {sup 154}Sm(n,2n){sup 153}Sm, {sup 152}Sm(n,γ){sup 153}Sm, {sup 186}W(d,2n){sup 186}Re, {sup 187}Re(γ,n){sup 186}Re, {sup 185}Re(n,γ){sup 186}Re and {sup 187}Re(n,γ){sup 188}Re reactions have been investigated in the different incident energy range of 0.003-34 MeV. Two-component exciton and generalised superfluid models of the TALYS 1.6 and exciton and generalised superfluid models of the EMPIRE 3.1 computer codes have been used to pre-equilibrium (PEQ) reaction calculations. The calculated production cross-section results have been compared with available experimental results existing in the experimental nuclear reaction database (EXFOR). Except the {sup 118}Sn(γ,n){sup 117}Sn, {sup 150}Nd(α,n){sup 153}Sm and {sup 185}Re(n,γ){sup 186}Re reactions, the two-component exciton model calculations of TALYS 1.6 code exhibit generally good agreement with the experimental measurements for all reactions used in this present study.
Van, Leerdam, J.; Adriaanse, P.I.; Horst, ter, J.P.; Roller, te, J.A.
2010-01-01
The user-friendly shell DROPLET, acronym for DRinkwater uit OPpervlaktewater- Landbouwkundig gebruik Evaluatie Tool, assists the Dutch Board for the Authorisation of Plant Protection Products and Biocides (Ctgb) in evaluating whether pesticides may exceed the 0.1 μg/L standard in one of the Dutch surface water abstraction points for drinking water production. It operationalises the methodology developed by a Dutch expert group described in Adriaanse et al (2008). This manual explains how to u...
International Nuclear Information System (INIS)
Using the quasi-classical trajectory (QCT) method, the product polarization at the collision energy of 46 kcal/mol is investigated for the reactions of F+LiH (v = 0, j = 0)→LiF+H and F+LiD (v = 0, j = 0)→LiF+D on the 2A' ground state potential energy surface (PES)[J. Chem. Phys. 106(1997)1013]. The distribution of P(θr), which represents the K and J' correlation, the dihedral angle distribution of K-K'-J' P(φr), the angular distribution P(θr, φr) and the four PDDCSs[(2π/σ)(dσ00/dωt), (2π/σ)(dσ20/dωt), (2π/σ)(dσ22+/dωt), (2π/σ)(dσ21-/dωt)] are presented and discussed. In addition, isotope effects are investigated. The results indicate that at the collision energy of 46 kcal/mol, with isotopic mass substitution, the orientation degree of LiF perpendicular to the scattering degree becomes stronger while the polarization degree of LiF perpendicular to K keeps almost changeless. In addition, the angular distribution of LiF strongly prefers forward scattering. (authors)
Energy Technology Data Exchange (ETDEWEB)
Mahmoudi, F
2004-06-01
The future CERN collider (LHC) has a fantastic potential of discovery, provided quantum chromodynamics can be quantitatively predicted. To do so, it is necessary to work at NLO approximation in order to reduce the dependence of the -cross-section on- the non-physical scales. To obtain results in this approximation, one has to calculate the cross-sections of the partonic subprocesses contributing to the studied reaction at the lowest order, and also the virtual corrections (loop corrections) and the real corrections. The calculation of the virtual corrections remains very complicated if the number of external particles is greater than four or if the external (internal) particles are massive. in this thesis, an automatic method which enables to calculate one loop diagrams with five external legs and which can be generalized to the case of massive particles is presented. In a first part, we describe different tools and methods necessary to such calculations. We then apply -them to the calculation of the gg {yields}{gamma}{gamma} g reaction, which interests the ATLAS and CMS experimentalists as the background for the Higgs boson search. We also give the explicit result for this amplitude for each helicity configuration in a compact form and a clearly gauge invariant representation. We finally present a phenomenological study of this reaction. (author)
On-Site was developed to provide modelers and model reviewers with prepackaged tools ("calculators") for performing site assessment calculations. The philosophy behind OnSite is that the convenience of the prepackaged calculators helps provide consistency for simple calculations,...
Institute of Scientific and Technical Information of China (English)
魏丹青; 赵建安; 金迁致
2012-01-01
The comparison of domestic and international calculation methods of CO2 emission from cement production has important reference value for establishing national calculation standards of CO2 emission from cement production.At present,international organizations like Intergovernmental Panel on Climate Change（IPCC）and World Business Council for Sustainable Development（WDCSD）have promulgated a series of universally applicable methods,and a number of developed countries have also proposed their own calculation systems.In this paper,we first briefly introduced the domestic and international calculation methods of CO2 emission from cement production,and performed a comparison of these methods from four aspects,including operational boundaries,raw material calcination emissions,fuel combustion emissions and indirect emissions.Then we made a discussion about the accuracy and applicability of those methods.The conclusions are as follows：1）Those systems are approximately same in the framework of calculation process,but there are differences in operational boundaries,calculating methods and CO2 emission factors;2）WBCSD-Cement Sustainability Initiative provides the methods of setting operational boundaries for countries or enterprises to choose the scope of accounting and reporting;3）On plant level,calcination CO2 can be calculated in two ways：based on the quantity and composition of the raw mix consumed or based on the clinker produced plus discarded dust.The two approaches are,in theory,equivalent.On country level,the latter approach is usually adopted;4）CO2 from fossil kiln fuels（coal,fuel oil and natural gas）is calculated based on fuel consumption,net calorific values,and CO2 emission factors.For China,low calorific value is applicable;5）On country level,the emissions of external production of electricity consumption should be included in the gross emissions,while indirect emission savings such as heat and power exports should be subtracted from the
International Nuclear Information System (INIS)
By means of the stacked foil technique 67 excitation functions of p induced reactions on the target elements Ti, V, Mn, Fe, Co, and Ni were measured in the energy range between 45 and 200 MeV. For residual nuclei with 42 <= A <= 60 and half-lives between 12 hours and 5.26 years cross sections could be determined whereby reactions of the type (p, n) to (p, 8p9n) contributed. On the base of the cross sections determined in this theses (together with the data of selected other authors) at set of cosmochemically relevant excitation functions for the description of the interaction of galactic protons with matter was established up to the GeV region, and model calculations for the production of cosmogenic nuclides in meteorites and cosmic dust were performed. For this depth dependent fluxes of galactic protons in meteorites were calculated, and production rates of radionuclides were determined from theses fluxes and the new excitation functions. (orig./HSI)
The calculation of pressure vessels
International Nuclear Information System (INIS)
The calculation guidelines of the Arbeitsgemeinschaft Druckbehaelter (task group for pressure vessels) have been revised with the following objective: conversion to international standards (SI), adaption to the latest state of guidelines for production and testing, revision of the contents of individual regulations. Another target of the cooperating interest groups of producers, operators, and supervisory bodies was a harmonization of the approaches for calculation with other German guidelines, in particular the Technische Regeln fuer Dampfkessel (technical regulations for steam boilers). (orig./RW)
International Nuclear Information System (INIS)
I took only few topics to investigate, some on which I had some personal interest, and others that I felt rather crucial for the design. In this document I report my calculations on these various subjects. Therefore this document represents my tangible contribution to TRISTAN design. I give in the following the list of the topics which are discussed in this document. 1. Increase of the vertical betatron emmitance by skew quadrupoles in the electron storage ring. 2. Bremsstrahlung. 3. Dipole correcting system for electron ring. 4. Wigglers at low energies 5. Steady state compensation of beam loading in the single beam mode in the electron storage ring. 6. Coupled bunch longitudinal instability for electron ring. 7. Ion production and trapping in the electron storage ring for TRISTAN. 8. Estimate of the longitudinal impedance for the TRISTAN electron storage ring. (author)
Configuration space Faddeev calculations
International Nuclear Information System (INIS)
The detailed study of few-body systems provides one of the most effective means for studying nuclear physics at subnucleon distance scales. For few-body systems the model equations can be solved numerically with errors less than the experimental uncertainties. We have used such systems to investigate the size of relativistic effects, the role of meson-exchange currents, and the importance of quark degrees of freedom in the nucleus. Complete calculations for momentum-dependent potentials have been performed, and the properties of the three-body bound state for these potentials have been studied. Few-body calculations of the electromagnetic form factors of the deuteron and pion have been carried out using a front-form formulation of relativistic quantum mechanics. The decomposition of the operators transforming convariantly under the Poincare group into kinematical and dynamical parts has been studies. New ways for constructing interactions between particles, as well as interactions which lead to the production of particles, have been constructed in the context of a relativistic quantum mechanics. To compute scattering amplitudes in a nonperturbative way, classes of operators have been generated out of which the phase operator may be constructed. Finally, we have worked out procedures for computing Clebsch-Gordan and Racah coefficients on a computer, as well as giving procedures for dealing with the multiplicity problem
Weldon Spring dose calculations
International Nuclear Information System (INIS)
In response to a request by the Oak Ridge Operations (ORO) Office of the Department of Energy (DOE) for assistance to the Department of the Army (DA) on the decommissioning of the Weldon Spring Chemical Plant, the Health and Safety Research Division of the Oak Ridge National Laboratory (ORNL) performed limited dose assessment calculations for that site. Based upon radiological measurements from a number of soil samples analyzed by ORNL and from previously acquired radiological data for the Weldon Spring site, source terms were derived to calculate radiation doses for three specific site scenarios. These three hypothetical scenarios are: a wildlife refuge for hunting, fishing, and general outdoor recreation; a school with 40 hr per week occupancy by students and a custodian; and a truck farm producing fruits, vegetables, meat, and dairy products which may be consumed on site. Radiation doses are reported for each of these scenarios both for measured uranium daughter equilibrium ratios and for assumed secular equilibrium. Doses are lower for the nonequilibrium case
Energy Technology Data Exchange (ETDEWEB)
Freyss, M.; Dorado, B.; Durinck, J. [CEA Cadarache (DEN/DEC/SESC/LLCC), 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Combustibles
2008-07-01
The aim of this work is to determine precisely the mechanisms of formation and migration of defects and fission products as well as the associated energies. Examples on uranium dioxide UO{sub 2} (standard nuclear fuel) and on uranium carbide UC (potential fuel for new generation reactors) are given. The obtained results are discussed and compared with the experimental results carried out. The ab initio method used is the Projector Augmented-Wave (PAW) method based on the density functional theory. The particular electronic properties of actinides are especially studied because, on account of their 5f orbitals more or less localized around the nucleus, it is difficult to model the actinide compounds by the DFT method. In particular, the modelling of the exchange-correlation interaction of the 5f electrons of UO{sub 2} requires approximations (as GGA+U) beyond those more currently used in ab initio calculations (LDA or GGA). (O.M.)
30 CFR 5.30 - Fee calculation.
2010-07-01
... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Fee calculation. 5.30 Section 5.30 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR TESTING, EVALUATION, AND APPROVAL OF MINING PRODUCTS FEES FOR TESTING, EVALUATION, AND APPROVAL OF MINING PRODUCTS § 5.30 Fee calculation....
Distillation Calculations with a Programmable Calculator.
Walker, Charles A.; Halpern, Bret L.
1983-01-01
Describes a three-step approach for teaching multicomponent distillation to undergraduates, emphasizing patterns of distribution as an aid to understanding the separation processes. Indicates that the second step can be carried out by programmable calculators. (A more complete set of programs for additional calculations is available from the…
Institute of Scientific and Technical Information of China (English)
曾志伟
2012-01-01
以洗涤液中的硫酸、磷酸，以及氨、硫酸铵、过磷酸钙生产硫磷酸铵复合肥，对硫磷酸铵物相组成、生产控制的关键因素进行探讨。通过实例定量测算得出：硫酸铵、过磷酸钙用量一定时，控制造粒机出口物料中和度n（N）／n（P）在1．70～1．85、硫酸消耗在220kg／t左右时，生产状况良好，设备运行良好。%Ammonium sulfate phosphate compound fertilizer is produced with sulfuric acid and phosphoric acid from cleaning mixture, ammonia, ammonium sulfate, SSP. The phase composition of ammonium sulfate phosphate and the key factors of production control are discussed. Based on the quantitatively calculation, it is concluded that: when the dosage of ammonium sulfate and single superphosphate is fixed, the material neutralization degree n(N) /n(P) in granulator export is 1.70- 1.85, sulfuric acid consumption is about 220 kg/t, the production condition and equipment operation are good.
Autistic Savant Calendar Calculators.
Patti, Paul J.
This study identified 10 savants with developmental disabilities and an exceptional ability to calculate calendar dates. These "calendar calculators" were asked to demonstrate their abilities, and their strategies were analyzed. The study found that the ability to calculate dates into the past or future varied widely among these calculators. Three…
Analytical model for release calculations in solid thin-foils ISOL targets
Egoriti, Luca; Ghys, Lars; Houngbo, Donald; Popescu, Lucia
2016-01-01
A detailed analytical model has been developed to simulate isotope-release curves from thin-foils ISOL targets. It involves the separate modelling of diffusion and effusion inside the target. The former has been modelled using both first and second Fick's law. The latter, effusion from the surface of the target material to the end of the ionizer, was simulated with the Monte Carlo code MolFlow+. The calculated delay-time distribution for this process was then fitted using a double-exponential function. The release curve obtained from the convolution of diffusion and effusion shows good agreement with experimental data from two different target geometries used at ISOLDE. Moreover, the experimental yields are well reproduced when combining the release fraction with calculated in-target production.
Institute of Scientific and Technical Information of China (English)
方恺; 董德明; 林卓; 沈万斌
2012-01-01
Net primary productivity (NPP) is a conceptual breakthrough in improving ecological footprint (EF) analysis. Three common features shared by the two assessment methods are the following: (1) an overlapping of space occupied. EF converts all consumption into land most of which also participates in global carbon cycle and is involved in net primary production; (2) the same basic measurement units adopted in them. EF that uses biological productivity as the basic measurement unit converts physical hectares into global hectares equal to the global average productivity, and NPP is employed as a common indicator of biological productivity. Therefore, both methods measure ecological sustainability directly based on biological productivity in essence; and (3 ) the complementary to each other for further information. They both emphasize the desirability of reducing the demand for nonrenewable resources. NPP can provide some missing information on analyzing sustainability when combined with EF. On the other hand, EF is able to compensate NPP for the lack of straightforwardness when tracking the maintenance of the biosphere's capacity. As a matter of fact, more and more studies attempt to include ocean, grassland and cropland's capacity for carbon sequestration into energy ecological footprint (EEF) assessment. However, EEF, the most important and disputed subject of EF, has rarely been applied in combination with NPP as modified methodologies. Of particular concern is how EEF is defined and what it actually measures, exclusion of a majority of land and water and failure to capture their actual capacity for carbon sequestration. Moreover, it illustrates the hypothetical land appropriation of energy consumption, which is inevitably in conflict with the actual appropriated land for biological production in one aggregation of EFs calculation. In this paper, a modified method for assessing EEF is developed based on global NPP, thereby primarily focusing on the interaction between
Design basis accident calculation problems
International Nuclear Information System (INIS)
Sudden failures of the primary circuit is the design basis accident of pressurized water reactors, being liable to affect the other two barriers separating the fission products from the environment. The calculation of the thermohydraulic behavior of the core and primary circuit is at present based, for the CEA, on the RELAP 4 code. However a second-generation code, POSEIDON, is being developed by the CEA, EDF and FRAMATOME to obtain a better description of the physical phenomena and a better estimate of safety margins. Other difficult problems arise in connection with the calculation of structural stresses and the behavior of the vessel during decompression
COST MEASUREMENT AND COST MANAGEMENT IN TARGET COSTING
Directory of Open Access Journals (Sweden)
Moisello Anna Maria
2012-07-01
Full Text Available Firms are coping with a competitive scenario characterized by quick changes produced by internationalization, concentration, restructuring, technological innovation processes and financial market crisis. On the one hand market enlargement have increased the number and the segmentation of customers and have raised the number of competitors, on the other hand technological innovation has reduced product life cycle. So firms have to adjust their management models to this scenario, pursuing customer satisfaction and respecting cost constraints. In a context where price is a variable fixed by the market, firms have to switch from the cost measurement logic to the cost management one, adopting target costing methodology. The target costing process is a price driven, customer oriented profit planning and cost management system. It works, in a cross functional way, from the design stage throughout all the product life cycle and it involves the entire value chain. The process implementation needs a costing methodology consistent with the cost management logic. The aim of the paper is to focus on Activity Based Costing (ABC application to target costing process. So: -it analyzes target costing logic and phases, basing on a literary review, in order to highlight the costing needs related to this process; -it shows, through a numerical example, how to structure a flexible ABC model â€“ characterized by the separation between variable, fixed in the short and fixed costs - that effectively supports target costing process in the cost measurement phase (drifting cost determination and in the target cost alignment; -it points out the effectiveness of the Activity Based Costing as a model of cost measurement applicable to the supplier choice and as a support for supply cost management which have an important role in target costing process. The activity based information allows a firm to optimize the supplier choice by following the method of minimizing the
Heterogeneous Calculation of ε
International Nuclear Information System (INIS)
A heterogeneous method of calculating the fast fission factor given by Naudet has been applied to the Carlvik - Pershagen definition of ε. An exact calculation of the collision probabilities is included in the programme developed for the Ferranti - Mercury computer
Personal Finance Calculations.
Argo, Mark
1982-01-01
Contains explanations and examples of mathematical calculations for a secondary level course on personal finance. How to calculate total monetary cost of an item, monthly payments, different types of interest, annual percentage rates, and unit pricing is explained. (RM)
Consolidated fuel shielding calculations
International Nuclear Information System (INIS)
Irradiated fuel radiation dose rate and radiation shielding requirements are calculated using a validated ISOSHLD-II model. Comparisons are made to experimental measurements. ISOSHLD-11 calculations are documented
Parallel nearest neighbor calculations
Trease, Harold
We are just starting to parallelize the nearest neighbor portion of our free-Lagrange code. Our implementation of the nearest neighbor reconnection algorithm has not been parallelizable (i.e., we just flip one connection at a time). In this paper we consider what sort of nearest neighbor algorithms lend themselves to being parallelized. For example, the construction of the Voronoi mesh can be parallelized, but the construction of the Delaunay mesh (dual to the Voronoi mesh) cannot because of degenerate connections. We will show our most recent attempt to tessellate space with triangles or tetrahedrons with a new nearest neighbor construction algorithm called DAM (Dial-A-Mesh). This method has the characteristics of a parallel algorithm and produces a better tessellation of space than the Delaunay mesh. Parallel processing is becoming an everyday reality for us at Los Alamos. Our current production machines are Cray YMPs with 8 processors that can run independently or combined to work on one job. We are also exploring massive parallelism through the use of two 64K processor Connection Machines (CM2), where all the processors run in lock step mode. The effective application of 3-D computer models requires the use of parallel processing to achieve reasonable "turn around" times for our calculations.
Ahrens, Thomas J.
2001-01-01
We examined the von Mises and Mohr-Coulomb strength models with and without damage effects and developed a model for dilatancy. The models and results are given in O'Keefe et al. We found that by incorporating damage into the models that we could in a single integrated impact calculation, starting with the bolide in the atmosphere produce final crater profiles having the major features found in the field measurements. These features included a central uplift, an inner ring, circular terracing and faulting. This was accomplished with undamaged surface strengths of approximately 0.1 GPa and at depth strengths of approximately 1.0 GPa. We modeled the damage in geologic materials using a phenomenological approach, which coupled the Johnson-Cook damage model with the CTH code geologic strength model. The objective here was not to determine the distribution of fragment sizes, but rather to determine the effect of brecciated and comminuted material on the crater evolution, fault production, ejecta distribution, and final crater morphology.
Calculating Clearances for Manipulators
Copeland, E. L.; Peticolas, J. D.; Ray, L. D.
1983-01-01
Set of algorithms rapidly calculates minimum safe clearances for remote manipulators. Such calculations are used in design of trajectories for manipulators to ensure they do not accidentally strike surrounding objects. Structural parts are considered as cylindrical shells having circular plane areas for ends. Clearance calculation method offers special benefits in industrial robotics, particularly in automated machining.
How Do Calculators Calculate Trigonometric Functions?
Underwood, Jeremy M.; Edwards, Bruce H.
How does your calculator quickly produce values of trigonometric functions? You might be surprised to learn that it does not use series or polynomial approximations, but rather the so-called CORDIC method. This paper will focus on the geometry of the CORDIC method, as originally developed by Volder in 1959. This algorithm is a wonderful…
Electronics reliability calculation and design
Dummer, Geoffrey W A; Hiller, N
1966-01-01
Electronics Reliability-Calculation and Design provides an introduction to the fundamental concepts of reliability. The increasing complexity of electronic equipment has made problems in designing and manufacturing a reliable product more and more difficult. Specific techniques have been developed that enable designers to integrate reliability into their products, and reliability has become a science in its own right. The book begins with a discussion of basic mathematical and statistical concepts, including arithmetic mean, frequency distribution, median and mode, scatter or dispersion of mea
Energy Technology Data Exchange (ETDEWEB)
Nagao, Yoshiharu [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
1998-03-01
In material testing reactors like the JMTR (Japan Material Testing Reactor) of 50 MW in Japan Atomic Energy Research Institute, the neutron flux and neutron energy spectra of irradiated samples show complex distributions. It is necessary to assess the neutron flux and neutron energy spectra of an irradiation field by carrying out the nuclear calculation of the core for every operation cycle. In order to advance core calculation, in the JMTR, the application of MCNP to the assessment of core reactivity and neutron flux and spectra has been investigated. In this study, in order to reduce the time for calculation and variance, the comparison of the results of the calculations by the use of K code and fixed source and the use of Weight Window were investigated. As to the calculation method, the modeling of the total JMTR core, the conditions for calculation and the adopted variance reduction technique are explained. The results of calculation are shown. Significant difference was not observed in the results of neutron flux calculations according to the difference of the modeling of fuel region in the calculations by K code and fixed source. The method of assessing the results of neutron flux calculation is described. (K.I.)
Thermodynamic calculation of a district energy cycle
International Nuclear Information System (INIS)
This paper presents a calculation model for a nuclear district energy circuit. Such a circuit means the combination of a steam reforming plant with heat supply from a high-temperature nuclear reactor and a methanation plant with heat production for district heating or electricity production. The model comprises thermodynamic calculations for the endothermic methane reforming reaction as well as the exothermic CO-hydrogenation in adiabatic reactors and allows the optimization of the district energy circuit under consideration. (orig.)
Direct calculation of wind turbine tip loss
DEFF Research Database (Denmark)
Wood, D.H.; Okulov, Valery; Bhattacharjee, D.
2016-01-01
. We develop three methods for the direct calculation of the tip loss. The first is the computationally expensive calculation of the velocities induced by the helicoidal wake which requires the evaluation of infinite sums of products of Bessel functions. The second uses the asymptotic evaluation of...
Electrical installation calculations advanced
Kitcher, Christopher
2013-01-01
All the essential calculations required for advanced electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practiceA step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3For apprentices and electrical installatio
Electronics Environmental Benefits Calculator
U.S. Environmental Protection Agency — The Electronics Environmental Benefits Calculator (EEBC) was developed to assist organizations in estimating the environmental benefits of greening their purchase,...
Electrical installation calculations basic
Kitcher, Christopher
2013-01-01
All the essential calculations required for basic electrical installation workThe Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike. The book provides a step-by-step guide to the successful application of electrical installation calculations required in day-to-day electrical engineering practice. A step-by-step guide to everyday calculations used on the job An essential aid to the City & Guilds certificates at Levels 2 and 3Fo
Waste Package Lifting Calculation
International Nuclear Information System (INIS)
The objective of this calculation is to evaluate the structural response of the waste package during the horizontal and vertical lifting operations in order to support the waste package lifting feature design. The scope of this calculation includes the evaluation of the 21 PWR UCF (pressurized water reactor uncanistered fuel) waste package, naval waste package, 5 DHLW/DOE SNF (defense high-level waste/Department of Energy spent nuclear fuel)--short waste package, and 44 BWR (boiling water reactor) UCF waste package. Procedure AP-3.12Q, Revision 0, ICN 0, calculations, is used to develop and document this calculation
Directory of Open Access Journals (Sweden)
Mohammed Abdulrahim Hamdi
2012-02-01
Full Text Available The mobile and wireless industry is entering an exciting time. Demand for mobile technology is growing at a tremendous rate. Corporations are deploying mobile applications that provide substantial business benefits, and consumers are readily adopting mobile data applications. We present scientific application for mobile phone in steps of software engineering project starting from data gathering, data analysis, designing, coding, packaging, testing and deploying, Mobile Scientific Calculator (MSC enable user to compute any mathematical operation by using this application in mobile phone without needing to use the calculator. Scientific calculator offers three keys the four mathematic operations, the four systems of digits and offering many of functions such as angles functions, power, factorial and other functions. Scientific calculator is suitable for many mobile phones which don t have scientific calculator in its applications, it provide simple design for dealing with its functions for all users. It operated on more than one mobile phone model.
The Impact of FDI on Innovation in Target Firms
Stiebale, Joel; Reize, Frank
2008-01-01
This paper contributes to the ongoing debate on the welfare effects of foreign direct investment by investigating the effects of cross-border mergers and acquisitions on innovation activities in target firms. The empirical analysis is based on survey and ownership data for a large sample of small- and medium- sized German firms. After controlling for endogeneity and selection bias, it is found that foreign takeovers have a large negative impact on the propensity to perform innovation activiti...
Collection of CASIM calculations
International Nuclear Information System (INIS)
Monte Carlo calculations of hadronic cascades at Fermilab have usually been done using the code CASIM written by A. Van Ginneken. These calculations are often performed to determine the quantity of shielding required for radiation protection purposes. A number of examples of such calculations have been presented previously. Several years of practical experience have led the author to develop the collection of additional cases included in the present report. These results along with those given earlier will serve as a useful reference. No attempt was made here to consider all possibilities; rather, the purpose was to develop a useful set of examples. Exceptionally intricate cases should, of course, receive individualized attention as appropriate
International Nuclear Information System (INIS)
We present GW calculations of molecules, ordered and disordered solids and interfaces, which employ an efficient contour deformation technique for frequency integration and do not require the explicit evaluation of virtual electronic states nor the inversion of dielectric matrices. We also present a parallel implementation of the algorithm, which takes advantage of separable expressions of both the single particle Green's function and the screened Coulomb interaction. The method can be used starting from density functional theory calculations performed with semilocal or hybrid functionals. The newly developed technique was applied to GW calculations of systems of unprecedented size, including water/semiconductor interfaces with thousands of electrons
Radioactive cloud dose calculations
International Nuclear Information System (INIS)
Radiological dosage principles, as well as methods for calculating external and internal dose rates, following dispersion and deposition of radioactive materials in the atmosphere are described. Emphasis has been placed on analytical solutions that are appropriate for hand calculations. In addition, the methods for calculating dose rates from ingestion are discussed. A brief description of several computer programs are included for information on radionuclides. There has been no attempt to be comprehensive, and only a sampling of programs has been selected to illustrate the variety available
Geogebra: Calculation of Centroid
Qamil Kllogjeri; Pellumb Kllogjeri
2012-01-01
Our paper is result of the research done in a special direction for solving problems of physics by using GeoGebra programme: calculation of centroid. Lots of simulations of physical phenomena from the class of Mechanics can be performed and computational problems can be solved with GeoGebra. GeoGebra offers many commands and one of them is the command “centroid” to calculate the coordinates of the centroid of a polygon but, we have created a new tool to calculate the coordinates of the centr...
nuclear reactor design calculations
International Nuclear Information System (INIS)
In this work , the sensitivity of different reactor calculation methods, and the effect of different assumptions and/or approximation are evaluated . A new concept named error map is developed to determine the relative importance of different factors affecting the accuracy of calculations. To achieve this goal a generalized, multigroup, multi dimension code UAR-DEPLETION is developed to calculate the spatial distribution of neutron flux, effective multiplication factor and the spatial composition of a reactor core for a period of time and for specified reactor operating conditions. The code also investigates the fuel management strategies and policies for the entire fuel cycle to meet the constraints of material and operating limitations
Algorithm project weight calculation aircraft
Directory of Open Access Journals (Sweden)
Г. В. Абрамова
2013-07-01
Full Text Available The paper describes the process of a complex technical object design on the example of the aircraft, using information technology such as CAD/CAM/CAE-systems, presents the basic models of aircraft which are developed in the process of designing and reflect the different aspects of its structure and function. The idea of control parametric model at complex technical object design is entered, which is a set of initial data for the development of design stations and enables the optimal complex technical object control at all stages of design using modern computer technology. The paper discloses a process of weight design, which is associated with all stages of development aircraft and its production. Usage of a scheduling algorithm that allows to organize weight calculations are carried out at various stages of planning and weighing options to optimize the use of available database of formulas and methods of calculation
Institute of Scientific and Technical Information of China (English)
吴福飞; 董双快; 宫经伟; 陈亮亮; 李东生; 侍克斌
2016-01-01
Powers theory proposes calculation method for the pure volume of cement hydration products, which does not apply to calculate the volume of cementitious materials with mineral admixture. The formula of cementitious materials volume was proposed that based on the basic principles of cement and mineral admixture hydration, and the proposed method of reliability was verified by the results of Powers theoretical model and volume fraction of cement hydration products. On this basis, the factor such as water-cement ratio, the ratio of admixture and types was further researched for the volumes of cementitious materials hydration products. Mixture in test were designed 2 water-cement ratio (0.30 and 0.40, respectively), two content (20% and 60%, respectively) of mineral admixture, and 3 kinds of mineral admixture (lithium slag, fly ash and steel slag, respectively), forming paste that was stirred according with the designed ratio in 5 mL centrifuge tube in a blender and curing to 1, 7, 14, 28, 60 and 90 d in curing room (temperature was (20±1)℃, humidity was not less than 95%), and then testing reaction extent of cement and mineral admixture (such as fly ash, steel slag. lithium slag) according with the chemical bound water and HCl dissolution method. The results showed that hydration extent of lithium slag, fly ash and steel slag at 28d decreased by 46.63%, 69.56% and 74.82% (P<0.05) when mineral admixture content varied from 20% to 60% and water-cement ratio was 0.30. Hydration extent of cement at 28 d was increased by 7.25% when water-cement ratio increased from 0.30 to 0.40. When mineral admixture content varied from 20% to 60%, hydration extent of lithium slag, fly ash and steel slag at 28 d increased by 24.14% 18.56%, 17.61% and 8.84%, 12.21%, and 29.37% (P<0.05), respectively. In contrast, the influence of the mineral admixture content was bigger than water-cement ratio for the hydration extent of composite cementitious materials. In different water-cement ratio
A Simple Calculator Algorithm.
Cook, Lyle; McWilliam, James
1983-01-01
The problem of finding cube roots when limited to a calculator with only square root capability is discussed. An algorithm is demonstrated and explained which should always produce a good approximation within a few iterations. (MP)
DEFF Research Database (Denmark)
Frederiksen, Morten
2014-01-01
Williamson’s characterisation of calculativeness as inimical to trust contradicts most sociological trust research. However, a similar argument is found within trust phenomenology. This paper re-investigates Williamson’s argument from the perspective of Løgstrup’s phenomenological theory of trust....... Contrary to Williamson, however, Løgstrup’s contention is that trust, not calculativeness, is the default attitude and only when suspicion is awoken does trust falter. The paper argues that while Williamson’s distinction between calculativeness and trust is supported by phenomenology, the analysis needs to...... take actual subjective experience into consideration. It points out that, first, Løgstrup places trust alongside calculativeness as a different mode of engaging in social interaction, rather conceiving of trust as a state or the outcome of a decision-making process. Secondly, the analysis must take...
Handout on shielding calculation
International Nuclear Information System (INIS)
In order to avoid the difficulties of the radioprotection supervisors in the tasks related to shielding calculations, is presented in this paper the basic concepts of shielding theory. It also includes exercises and examples. (author)
IRIS core criticality calculations
International Nuclear Information System (INIS)
Three-dimensional Monte Carlo computer code KENO-VI of CSAS26 sequence of SCALE-4.4 code system was applied for pin-by-pin calculations of the effective multiplication factor for the first cycle IRIS reactor core. The effective multiplication factors obtained by the above mentioned Monte Carlo calculations using 27-group ENDF/B-IV library and 238-group ENDF/B-V library have been compared with the effective multiplication factors achieved by HELIOS/NESTLE, CASMO/SIMULATE, and modified CORD-2 nodal calculations. The results of Monte Carlo calculations are found to be in good agreement with the results obtained by the nodal codes. The discrepancies in effective multiplication factor are typically within 1%. (author)
Unit Cost Compendium Calculations
U.S. Environmental Protection Agency — The Unit Cost Compendium (UCC) Calculations raw data set was designed to provide for greater accuracy and consistency in the use of unit costs across the USEPA...
Current interruption transients calculation
Peelo, David F
2014-01-01
Provides an original, detailed and practical description of current interruption transients, origins, and the circuits involved, and how they can be calculated Current Interruption Transients Calculationis a comprehensive resource for the understanding, calculation and analysis of the transient recovery voltages (TRVs) and related re-ignition or re-striking transients associated with fault current interruption and the switching of inductive and capacitive load currents in circuits. This book provides an original, detailed and practical description of current interruption transients, origins,
Reactor lattice transport calculations
International Nuclear Information System (INIS)
The present lecture is a continuation of the lecture on Introduction to the Neutron Transport Phenomena. It comprises three aspects of lattice calculations. First the idea of a reactor lattice is introduced. Then the main definitions used in reactor lattice analysis are given, and finally two basic methods applied for solution of the transport equations are defined. Several remarks on secondary results from lattice transport calculations are added. (author)
Electrical installation calculations
Watkins, AJ
2006-01-01
Designed to provide a step by step guide to successful application of the electrical installation calculations required in day to day electrical engineering practice, the Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both apprentices and professional electrical installation engineers alike.Now in its seventh edition, Volume 1 has been fully updated to meet the requirements of the 2330 Level 2 Certificate in Electrotechnical Technology from City & Guilds, and will also prove a vi
Geometric unsharpness calculations
Energy Technology Data Exchange (ETDEWEB)
Anderson, D.J. [International Training and Education Group (INTEG), Oakville, Ontario (Canada)
2008-07-15
The majority of radiographers' geometric unsharpness calculations are normally performed with a mathematical formula. However, a majority of codes and standards refer to the use of a nomograph for this calculation. Upon first review, the use of a nomograph appears more complicated but with a few minutes of study and practice it can be just as effective. A review of this article should provide enlightenment. (author)
Three-dimensional cavity calculations
International Nuclear Information System (INIS)
The existence of a code that solves for the resonant electromagnetic modes of oscillation in arbitrarily-shaped three-dimensional cavities opens new possibilities in rf-structure analysis and research. The URMEL-3D code, the product of a multi-year collaboration between DESY, KFA-Juelich, and Los Alamos, has been used in some exploratory studies to determine the feasibility of using a 3-D code to calculate the properties of several practical rf structures. The results are reported here for three cases: the jungle gym, two coupled cavities, and a waveguide-cavity coupling problem
Uncertainty calculations made easier
Energy Technology Data Exchange (ETDEWEB)
Hogenbirk, A.
1994-07-01
The results are presented of a neutron cross section sensitivity/uncertainty analysis performed in a complicated 2D model of the NET shielding blanket design inside the ITER torus design, surrounded by the cryostat/biological shield as planned for ITER. The calculations were performed with a code system developed at ECN Petten, with which sensitivity/uncertainty calculations become relatively simple. In order to check the deterministic neutron transport calculations (performed with DORT), calculations were also performed with the Monte Carlo code MCNP. Care was taken to model the 2.0 cm wide gaps between two blanket segments, as the neutron flux behind the vacuum vessel is largely determined by neutrons streaming through these gaps. The resulting neutron flux spectra are in excellent agreement up to the end of the cryostat. It is noted, that at this position the attenuation of the neutron flux is about 1 l orders of magnitude. The uncertainty in the energy integrated flux at the beginning of the vacuum vessel and at the beginning of the cryostat was determined in the calculations. The uncertainty appears to be strongly dependent on the exact geometry: if the gaps are filled with stainless steel, the neutron spectrum changes strongly, which results in an uncertainty of 70% in the energy integrated flux at the beginning of the cryostat in the no-gap-geometry, compared to an uncertainty of only 5% in the gap-geometry. Therefore, it is essential to take into account the exact geometry in sensitivity/uncertainty calculations. Furthermore, this study shows that an improvement of the covariance data is urgently needed in order to obtain reliable estimates of the uncertainties in response parameters in neutron transport calculations. (orig./GL).
Uncertainty calculations made easier
International Nuclear Information System (INIS)
The results are presented of a neutron cross section sensitivity/uncertainty analysis performed in a complicated 2D model of the NET shielding blanket design inside the ITER torus design, surrounded by the cryostat/biological shield as planned for ITER. The calculations were performed with a code system developed at ECN Petten, with which sensitivity/uncertainty calculations become relatively simple. In order to check the deterministic neutron transport calculations (performed with DORT), calculations were also performed with the Monte Carlo code MCNP. Care was taken to model the 2.0 cm wide gaps between two blanket segments, as the neutron flux behind the vacuum vessel is largely determined by neutrons streaming through these gaps. The resulting neutron flux spectra are in excellent agreement up to the end of the cryostat. It is noted, that at this position the attenuation of the neutron flux is about 1 l orders of magnitude. The uncertainty in the energy integrated flux at the beginning of the vacuum vessel and at the beginning of the cryostat was determined in the calculations. The uncertainty appears to be strongly dependent on the exact geometry: if the gaps are filled with stainless steel, the neutron spectrum changes strongly, which results in an uncertainty of 70% in the energy integrated flux at the beginning of the cryostat in the no-gap-geometry, compared to an uncertainty of only 5% in the gap-geometry. Therefore, it is essential to take into account the exact geometry in sensitivity/uncertainty calculations. Furthermore, this study shows that an improvement of the covariance data is urgently needed in order to obtain reliable estimates of the uncertainties in response parameters in neutron transport calculations. (orig./GL)
Inventory calculation for an irradiated HTGR fuel element
International Nuclear Information System (INIS)
In this report the inventories of some gamma-active fission products were calculated for an irradiated capsule. The number of heavy metal atoms (fissile and fertile), as well as the number of atoms for fission products are calculated and given after each irradiation cycle. The energy produced at each irradiation period is calculated and given in watts. The burnup due to each element that underwent fission and the total burnup was also calculated. 1 fig., 19 tab
On the calculation of soft phase space integral
Zhu, Hua
2015-01-01
The recent discovery of the Higgs boson at the LHC attracts much attention to the precise calculation of its production cross section in quantum chromodynamics. In this work, we discuss the calculation of soft triple-emission phase space integral, which is an essential ingredient in the recently calculated soft-virtual corrections to Higgs boson production at next-to-next-to-next-to-leading order. The main techniques used this calculation are method of differential equation for Feynman integr...
Progress on theoretical calculation
International Nuclear Information System (INIS)
The calculation program NPPD-2 of neutron reaction data in the energy region from 10-11 to 20 MeV has been researched with extending the energy from 5 to 20 MeV. In this program, the cascade γ-de-excitations of the compound nucleus and residual nucleus are described by means of the Troubetzkoy's statistical model and the conservation relations of angular momentum and parity are are considered. This program may be used for the calculations of the natural element, with the number of isotopes less than 10. The program has been finished and the calculations for oxygen are being done in order to test the program. The reaction channels in n + 40Ca, which considered in NPPD-2, are presented
Daylight calculations in practice
DEFF Research Database (Denmark)
Iversen, Anne; Roy, Nicolas; Hvass, Mette;
The aim of the project was to obtain a better understanding of what daylight calculations show and also to gain knowledge of how the different daylight simulation programs perform compared with each other. Experience has shown that results for the same room, obtained from two daylight simulation...... programs can give different results. This can be due to restrictions in the program itself and/or be due to the skills of the persons setting up the models. This is crucial as daylight calculations are used to document that the demands and recommendations to daylight levels outlined by building authorities....... The aim of the project was to obtain a better understanding of what daylight calculations show and also to gain knowledge of how the different daylight simulation programs perform compared with each other. Furthermore the aim was to provide knowledge of how to build up the 3D models that were to be...
Geogebra: Calculation of Centroid
Directory of Open Access Journals (Sweden)
Qamil Kllogjeri
2012-09-01
Full Text Available Our paper is result of the research done in a special direction for solving problems of physics by using GeoGebra programme: calculation of centroid. Lots of simulations of physical phenomena from the class of Mechanics can be performed and computational problems can be solved with GeoGebra. GeoGebra offers many commands and one of them is the command “centroid” to calculate the coordinates of the centroid of a polygon but, we have created a new tool to calculate the coordinates of the centroid of a plane region bounded by curves. Our work is part of the passionate work of many GeoGebra users which will result with a very rich fund of GeoGebra virtual tools, examples and experiences that will be worldwidely available for many teachers and practioners.
Population dose calculation technique
International Nuclear Information System (INIS)
An original method is suggested for calculating the population doses from gas and aerosol radioactive releases. The method is based on the assumption of uniform population and arable land distribution. The validity of this assumption has been proved for a rather large condition range. Though, some modified formulae are given to take into account the non-uniformity of population distribution, connected with large cities, on the one hand, and with woods, shores, regional borders, on the other hand. Employment of the suggested method results in an apriciable calculation accuracy rise for the long-living slowly precipitating radionuclides as compared with the existing methods
Big Bang Nucleosynthesis Calculation
Kurki-Suonio, H
2001-01-01
I review standard big bang nucleosynthesis and some versions of nonstandard BBN. The abundances of the primordial isotopes D, He-3, and Li-7 produced in standard BBN can be calculated as a function of the baryon density with an accuracy of about 10%. For He-4 the accuracy is better than 1%. The calculated abundances agree fairly well with observations, but the baryon density of the universe cannot be determined with high precision. Possibilities for nonstandard BBN include inhomogeneous and antimatter BBN and nonzero neutrino chemical potentials.
Electrical installation calculations
Watkins, AJ
2006-01-01
Designed to provide a step by step guide to successful application of the electrical installation calculations required in day to day electrical engineering practice, the Electrical Installation Calculations series has proved an invaluable reference for over forty years, for both Foundation and Modern Apprentices, and professional electrical installation engineers alike.Now in its sixth edition, Volume 2 has been fully updated to meet the requirements of the 2330 Level 3 Certificate in Electrotechnical Technology from City & Guilds, and will also prove a vital purchase for students of Level 3
Three recent TDHF calculations
International Nuclear Information System (INIS)
Three applications of TDHF are discussed. First, vibrational spectra of a post grazing collision 40Ca nucleus is examined and found to contain many high energy components, qualitatively consistent with recent Orsay experiments. Second, the fusion cross section in energy and angular momentum are calculated for 16O + 24Mg to exhibit the parameters of the low l window for this system. A sensitivity of the fusion cross section to the effective two body potential is discussed. Last, a preliminary analysis of 86Kr + 139La at E/sub lab/ = 505 MeV calculated in the frozen approximation is displayed, compared to experiment and discussed
Noordzij, Marlies; Dekker, Friedo W.; Zoccali, Carmine; Jager, Kitty J.
2011-01-01
The sample size is the number of patients or other experimental units that need to be included in a study to answer the research question. Pre-study calculation of the sample size is important; if a sample size is too small, one will not be able to detect an effect, while a sample that is too large may be a waste of time and money. Methods to calculate the sample size are explained in statistical textbooks, but because there are many different formulas available, it can be difficult for inves...
Institute of Scientific and Technical Information of China (English)
无
2011-01-01
Compared with ellipse cavity, the spoke cavity has many advantages, especially for the low and medium beam energy. It will be used in the superconductor accelerator popular in the future. Based on the spoke cavity, we design and calculate an accelerator
Water vapor pressure calculation.
Hall, J R; Brouillard, R G
1985-06-01
Accurate calculation of water vapor pressure for systems saturated with water vapor can be performed using the Goff-Gratch equation. A form of the equation that can be adapted for computer programming and for use in electronic databases is provided. PMID:4008425
Languages for structural calculations
International Nuclear Information System (INIS)
The differences between human and computing languages are recalled. It is argued that they are to some extent structured in antagonistic ways. Languages in structural calculation, in the past, present, and future, are considered. The contribution of artificial intelligence is stressed
Calendrical Calculation and Intelligence.
O'Connor, Neil; Cowan, Richard; Samella, Katerina
2000-01-01
Studied the ability to name the days of the week for dates in the past and future (calendrical calculation) of 10 calendrical savants with Wechlser Adult Intelligence Scale scores from 50 to 97. Results suggest that although low intelligence does not prevent the development of this skill, the talent depends on general intelligence. (SLD)
PROSPECTS OF MANAGEMENT ACCOUNTING AND COST CALCULATION
Directory of Open Access Journals (Sweden)
Marian ŢAICU
2014-11-01
Full Text Available Progress in improving production technology requires appropriate measures to achieve an efficient management of costs. This raises the need for continuous improvement of management accounting and cost calculation. Accounting information in general, and management accounting information in particular, have gained importance in the current economic conditions, which are characterized by risk and uncertainty. The future development of management accounting and cost calculation is essential to meet the information needs of management.
Source term calculations of the ALMR
International Nuclear Information System (INIS)
This report contains the results of a thermochemical study on the aspects of fission product release in sodium cooled reactors. An overview of the relevant thermochemical data (excess Gibbs energies of mixing) of sodium systems is presented. Phase equilibrium calculations of the thermochemical behavior of one fuel pin and of the reactor vessel were performed. In these calculations, 30 elements and approximately 100 compounds are involved. (orig.)
Source term calculations of the ALMR
Energy Technology Data Exchange (ETDEWEB)
Schram, R.P.C.; Cordfunke, E.H.P.; Huntelaar, M.E.
1995-07-01
This report contains the results of a thermochemical study on the aspects of fission product release in sodium cooled reactors. An overview of the relevant thermochemical data (excess Gibbs energies of mixing) of sodium systems is presented. Phase equilibrium calculations of the thermochemical behavior of one fuel pin and of the reactor vessel were performed. In these calculations, 30 elements and approximately 100 compounds are involved. (orig.).
Noble gas sputtering calculations using TRIM
International Nuclear Information System (INIS)
In conjunction with our experimental work on saddle field ion sputtering, we have attempted to apply the Monte Carlo program TRIM (Transport of Ions in Matter) to calculate the sputter yields for a variety of noble gas sputtering applications. Comparison with experiments are shown. Information extracted from these analyses have proved useful in optimizing the experimental sputtering parameters. Calculated sputter yields obtained utilizing TRIM are presented for noble gas sputtering of a variety of materials common to nuclear target production
A revised calculational model for fission
International Nuclear Information System (INIS)
A semi-empirical parametrization has been developed to calculate the fission contribution to evaporative de-excitation of nuclei with a very wide range of charge, mass and excitation-energy and also the nuclear states of the scission products. The calculational model reproduces measured values (cross-sections, mass distributions, etc.) for a wide range of fissioning systems: Nuclei from Ta to Cf, interactions involving nucleons up to medium energy and light ions. (author)
PROSPECTS OF MANAGEMENT ACCOUNTING AND COST CALCULATION
Marian ŢAICU
2014-01-01
Progress in improving production technology requires appropriate measures to achieve an efficient management of costs. This raises the need for continuous improvement of management accounting and cost calculation. Accounting information in general, and management accounting information in particular, have gained importance in the current economic conditions, which are characterized by risk and uncertainty. The future development of management accounting and cost calculation is essential to me...
A revised calculational model for fission
Energy Technology Data Exchange (ETDEWEB)
Atchison, F.
1998-09-01
A semi-empirical parametrization has been developed to calculate the fission contribution to evaporative de-excitation of nuclei with a very wide range of charge, mass and excitation-energy and also the nuclear states of the scission products. The calculational model reproduces measured values (cross-sections, mass distributions, etc.) for a wide range of fissioning systems: Nuclei from Ta to Cf, interactions involving nucleons up to medium energy and light ions. (author)
International Nuclear Information System (INIS)
Maxwell-averaged reaction rates (sigma v-bar) are presented for 24 interactions between 1H, 2H, 3H, 3He, 4He, 6Li, 7Li, 10B, and 11B ions. The reactions rates are calculated by use of the evaluated data of the LLL Evaluated Nuclear Data Library (ENDL). 5 figures, 5 tables
Quantifying Interobserver Variation in Target Definition in Palliative Radiotherapy
International Nuclear Information System (INIS)
Purpose: To describe the degree of interobserver and intraobserver variability in target and field definition when using three-dimensional (3D) volume- vs. two-dimensional (2D) field-based planning. Methods and Materials: Standardized case scenario and diagnostic imaging for 9 palliative cases (3 bone metastases, 3 palliative lung cancer, and 3 abdominal pelvis soft-tissue disease) were presented to 5 study radiation oncologists. After a decision on what the intended anatomic target should be, observers created two sets of treatment fields, first using a 2D field-based and then a 3D volume-based planning approach. Percent overlap, under-coverage, and over-coverage were used to describe interobserver and intraobserver variations in target definition. Results: The degree of interobserver variation for 2D and 3D planning was similar with a degree of overlap of 76% (range, 56%-85%) and 74% (range, 55%-88%), respectively. When comparing the treatment fields defined by the same observer using the two different planning methods, the mean degree of overlap was 78%; over-coverage, 22%; and under-coverage, 41%. There was statistically significantly more under-coverage when field-based planning was used for bone metastases (33%) vs. other anatomic sites (16%) (p = 0.02). In other words, 2D planning is more likely to result in geographic misses in bone metastases compared with other areas. Conclusions: In palliative radiotherapy clinically significant interobserver and intraobserver variation existed when using both field- and volume-based planning approaches. Strategies that would reduce this variability deserve further investigation.
Optimization calculations at TR-2
International Nuclear Information System (INIS)
Full text: The main objective of the optimization calculations at TR-2 is to increase the radioisotope production (Tc-99m, I-131). Irradiation time and location were optimized separately. A second objective of this study is to obtain similar activities in the irradiated samples irrespective of the irradiation positions. This study also includes the maximization of the discharge burnup levels of the HEU elements in a mixed HEU-LEU core, so both safe and economical usage of the reactor is attained. Five group structure is used for the burnup dependent cross-section libraries that are generated by EPRI-CELL code. The RABANL integral transport option of MC2-2 code was used to accurately account for the resonance self-shielding of U-238. Transport corrected effective cross sections were used for the control rod regions. The data for Mo, Tc and Te isotopes were not available in this library, so new data were generated using GGC-4 and ANISN codes. In order to have a better understanding of the neutronic interactions, especially in the epithermal energy range, 9 group structure for the cross-section libraries of all the isotopes in the core have been generated with the fore mentioned codes. 2D diffusion-depletion code GEREBUS is used for the reactivity and burnup calculations. The 9 group calculations gave higher activity values then 5 group results, but the relative variations between different core positions remained the same, as could be expected. Many new core designs and various irradiation positions have been investigated for the above mentioned purposes. The reactor core was designed as compact as possible, in order to have higher fluxes for the irradiation samples. New graphite and Be reflectors have been added to the periphery of the core to enhance the reactivity and the discharge burnup levels. The water boxes which are used for the irradiation purposes have been moved from periphery to the inside of the reactor core. These modifications have yielded higher
PIC: Protein Interactions Calculator
Tina, KG; Bhadra, R.; Srinivasan, N.
2007-01-01
Interactions within a protein structure and interactions between proteins in an assembly are essential considerations in understanding molecular basis of stability and functions of proteins and their complexes. There are several weak and strong interactions that render stability to a protein structure or an assembly. Protein Interactions Calculator (PIC) is a server which, given the coordinate set of 3D structure of a protein or an assembly, computes various interactions such as disulphide bo...
Biogas - the calculable energy
Kith, Károly; Nagy, Orsolya; Balla, Zoltán; Tamás, András
2015-04-01
EU actions against climate change are rising energy prices, both have emphasized the use of renewable energy,increase investments and energy efficiency. A number of objectives formulated in the EC decree no. 29/2009 by 2020. This document is based on the share of renewable energies in energy consumption should be increased to 20% (EC, 2009). The EU average is 20% but the share of renewables vary from one member state to another. In Hungary in 2020, 14.65% renewable energy share is planned to be achieved. According to the latest Eurostat data, the share of renewable energy in energy consumption of the EU average was 14.1%, while in Hungary, this share was 9.6% in 2012. (EUROSTAT, 2014). The use of renewable energy plant level is influenced by several factors. The most important of these is the cost savings and efficiency gains. Hungarian investments in renewable energy production usually have high associated costs and the payback period is substantially more than five years, depending on the support rate. For example, the payback period is also influenced by the green electricity generated feed prices, which is one of the lowest in Hungary compared the Member States of the European Union. Consequently, it is important to increase the production of green energy. Nowadays, predictable biogas energy is an outstanding type of decentralized energy production. It follows directly that agricultural by-products can be used to produce energy and they also create jobs by the construction of a biogas plant. It is important to dispose of and destroy hazardous and noxious substances in energy production. It follows from this that the construction of biogas plants have a positive impact, in addition to green energy which is prepared to reduce the load on the environment. The production of biogas and green electricity is one of the most environment friendly forms of energy production. Biogas production also has other important ecological effects, such as the substitution of
Energy Technology Data Exchange (ETDEWEB)
Smink, W.; Pellikaan, W.F.; Van der Kolk, L.J. [Feed Innovation Services, Aarle-Rixtel (Netherlands); Van der Hoek, K.W. [Rijksinstituut voor Volksgezondheid en Milieu RIVM, Bilthoven (Netherlands)
2004-07-01
Following the IPCC GPG Guidelines the enteric fermentation emission is calculated as a percentage of the gross energy intake in cattle feedstuffs. The energy consumption for maintenance, activity, growth, lactation and pregnancy is described in detail. Combining this with the average rations for cattle the methane emissions are calculated. The report presents for the period 1990-2002 for all cattle categories the methane emission resulting from enteric fermentation. [Dutch] Volgens de IPCC-GPG methode wordt de methaanemissie berekend als percentage van de door het dier opgenomen bruto energie met het voer. Het rapport beschrijft in detail de benodigde energie voor onderhoud, activiteit, groei, lactatie en dracht. Met behulp van de rantsoenen van het Nederlandse rundvee wordt vervolgens de bruto energie opname berekend. Het rapport presenteert voor de volledige periode 1990-2002 voor alle rundveecategorieen de methaanemissie als gevolg van pensfermentatie.
Institute of Scientific and Technical Information of China (English)
赵晓刚
2012-01-01
Combined with production practice, calculating methods of mixed oil quantity in the batch transportation product pipeline were mainly introduced as well as theoretical formula, corrected theoretical formula and empirical formula. Through example calculation, different formulae were compared. Then, factors to influence mixed oil quantity were analyzed, and measures to reduce mixed oil quantity were put forward.%结合生产实际,重点介绍了成品油顺序输送管道混油量的计算方法,包括理论公式、修正的理论公式以及经验公式,并进行了相应的实例计算,对各种计算公式进行的比较,分析了混油量的影响因素,提出了减少混油量的措施.
COSTS CALCULATION OF TARGET COSTING METHOD
UNGUREANU Sebastian
2014-01-01
Cost information system plays an important role in every organization in the decision making process. An important task of management is ensuring control of the operations, processes, sectors, and not ultimately on costs. Although in achieving the objectives of an organization compete more control systems (production control, quality control, etc.), the cost information system is important because monitors results of the other. Detailed analysis of costs, production cost calculation, quantifi...
Covariant method for calculating helicity amplitudes
International Nuclear Information System (INIS)
We present an alternative approach for calculating helicity amplitudes for processes involving both massless and massive fermions. With this method one can easily obtain covariant expressions for the helicity amplitudes. The final expressions involve only four-vector products and are independent of the basis for γ matrices or specific form of the spinors. We use the method to obtain the helicity amplitudes for several processes involving top quark production. copyright 1996 The American Physical Society
Calculations in furnace technology
Davies, Clive; Hopkins, DW; Owen, WS
2013-01-01
Calculations in Furnace Technology presents the theoretical and practical aspects of furnace technology. This book provides information pertinent to the development, application, and efficiency of furnace technology. Organized into eight chapters, this book begins with an overview of the exothermic reactions that occur when carbon, hydrogen, and sulfur are burned to release the energy available in the fuel. This text then evaluates the efficiencies to measure the quantity of fuel used, of flue gases leaving the plant, of air entering, and the heat lost to the surroundings. Other chapters consi
Zero Temperature Hope Calculations
International Nuclear Information System (INIS)
The primary purpose of the HOPE code is to calculate opacities over a wide temperature and density range. It can also produce equation of state (EOS) data. Since the experimental data at the high temperature region are scarce, comparisons of predictions with the ample zero temperature data provide a valuable physics check of the code. In this report we show a selected few examples across the periodic table. Below we give a brief general information about the physics of the HOPE code. The HOPE code is an ''average atom'' (AA) Dirac-Slater self-consistent code. The AA label in the case of finite temperature means that the one-electron levels are populated according to the Fermi statistics, at zero temperature it means that the ''aufbau'' principle works, i.e. no a priory electronic configuration is set, although it can be done. As such, it is a one-particle model (any Hartree-Fock model is a one particle model). The code is an ''ion-sphere'' model, meaning that the atom under investigation is neutral within the ion-sphere radius. Furthermore, the boundary conditions for the bound states are also set at the ion-sphere radius, which distinguishes the code from the INFERNO, OPAL and STA codes. Once the self-consistent AA state is obtained, the code proceeds to generate many-electron configurations and proceeds to calculate photoabsorption in the ''detailed configuration accounting'' (DCA) scheme. However, this last feature is meaningless at zero temperature. There is one important feature in the HOPE code which should be noted; any self-consistent model is self-consistent in the space of the occupied orbitals. The unoccupied orbitals, where electrons are lifted via photoexcitation, are unphysical. The rigorous way to deal with that problem is to carry out complete self-consistent calculations both in the initial and final states connecting photoexcitations, an enormous computational task. The Amaldi correction is an attempt to address this problem by distorting the
Linewidth calculations and simulations
Strandberg, Ingrid
2016-01-01
We are currently developing a new technique to further enhance the sensitivity of collinear laser spectroscopy in order to study the most exotic nuclides available at radioactive ion beam facilities, such as ISOLDE at CERN. The overall goal is to evaluate the feasibility of the new method. This report will focus on the determination of the expected linewidth (hence resolution) of this approach. Different effects which could lead to a broadening of the linewidth, e.g. the ions' energy spread and their trajectories inside the trap, are studied with theoretical calculations as well as simulations.
Lopez, Cesar
2015-01-01
MATLAB is a high-level language and environment for numerical computation, visualization, and programming. Using MATLAB, you can analyze data, develop algorithms, and create models and applications. The language, tools, and built-in math functions enable you to explore multiple approaches and reach a solution faster than with spreadsheets or traditional programming languages, such as C/C++ or Java. This book is designed for use as a scientific/business calculator so that you can get numerical solutions to problems involving a wide array of mathematics using MATLAB. Just look up the function y
International Nuclear Information System (INIS)
In this paper, excerpts of the 'Core Design', 'Computational Chains' and 'Qualification of Computational Chains' lectures are presented. Nuclear reactor design basic concepts as power distribution and reactivity are defined and analyzed both from the theoretical and the computational point of view. Emphasis is put on the physical meaning and sensitivity of both 'observables' to design parameters. Computational aspects, mainly as regards the effects of the heterogeneity in space and energy in reactor calculations, are afforded too. Structure and qualification of computational code packages are discussed and a practical application to the FRAMATOME SCIENCE advanced computational chain is supplied. (author)
International Nuclear Information System (INIS)
Several Monte Carlo techniques are compared in the transport of neutrons of different source energies through two different deep-penetration problems each with two parts. The first problem involves transmission through a 200-cm concrete slab. The second problem is a 900 bent pipe jacketed by concrete. In one case the pipe is void, and in the other it is filled with liquid sodium. Calculations are made with two different Los Alamos Monte Carlo codes: the continuous-energy code MCNP and the multigroup code MCMG
21 CFR 211.103 - Calculation of yield.
2010-04-01
... 21 Food and Drugs 4 2010-04-01 2010-04-01 false Calculation of yield. 211.103 Section 211.103 Food... § 211.103 Calculation of yield. Actual yields and percentages of theoretical yield shall be determined... the drug product. Such calculations shall either be performed by one person and independently...
9 CFR 124.20 - Patent term extension calculation.
2010-01-01
... OF AGRICULTURE VIRUSES, SERUMS, TOXINS, AND ANALOGOUS PRODUCTS; ORGANISMS AND VECTORS PATENT TERM RESTORATION Regulatory Review Period § 124.20 Patent term extension calculation. (a) As provided in 37 CFR 1... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Patent term extension calculation....
Multilayer optical calculations
Byrnes, Steven J
2016-01-01
When light hits a multilayer planar stack, it is reflected, refracted, and absorbed in a way that can be derived from the Fresnel equations. The analysis is treated in many textbooks, and implemented in many software programs, but certain aspects of it are difficult to find explicitly and consistently worked out in the literature. Here, we derive the formulas underlying the transfer-matrix method of calculating the optical properties of these stacks, including oblique-angle incidence, absorption-vs-position profiles, and ellipsometry parameters. We discuss and explain some strange consequences of the formulas in the situation where the incident and/or final (semi-infinite) medium are absorptive, such as calculating $T>1$ in the absence of gain. We also discuss some implementation details like complex-plane branch cuts. Finally, we derive modified formulas for including one or more "incoherent" layers, i.e. very thick layers in which interference can be neglected. This document was written in conjunction with ...
The conundrum of calculating carbon footprints
DEFF Research Database (Denmark)
Strobel, Bjarne W.; Erichsen, Anders Christian; Gausset, Quentin
2016-01-01
A pre-condition for reducing global warming is to minimise the emission of greenhouse gasses (GHGs). A common approach to informing people about the link between behaviour and climate change rests on developing GHG calculators that quantify the ‘carbon footprint’ of a product, a sector or an actor...
Difference equations in massive higher order calculations
International Nuclear Information System (INIS)
The calculation of massive 2-loop operator matrix elements, required for the higher order Wilson coefficients for heavy flavor production in deeply inelastic scattering, leads to new types of multiple infinite sums over harmonic sums and related functions, which depend on the Mellin parameter N. We report on the solution of these sums through higher order difference equations using the summation package Sigma. (orig.)
Molecular Dynamics Calculations
1996-01-01
The development of thermodynamics and statistical mechanics is very important in the history of physics, and it underlines the difficulty in dealing with systems involving many bodies, even if those bodies are identical. Macroscopic systems of atoms typically contain so many particles that it would be virtually impossible to follow the behavior of all of the particles involved. Therefore, the behavior of a complete system can only be described or predicted in statistical ways. Under a grant to the NASA Lewis Research Center, scientists at the Case Western Reserve University have been examining the use of modern computing techniques that may be able to investigate and find the behavior of complete systems that have a large number of particles by tracking each particle individually. This is the study of molecular dynamics. In contrast to Monte Carlo techniques, which incorporate uncertainty from the outset, molecular dynamics calculations are fully deterministic. Although it is still impossible to track, even on high-speed computers, each particle in a system of a trillion trillion particles, it has been found that such systems can be well simulated by calculating the trajectories of a few thousand particles. Modern computers and efficient computing strategies have been used to calculate the behavior of a few physical systems and are now being employed to study important problems such as supersonic flows in the laboratory and in space. In particular, an animated video (available in mpeg format--4.4 MB) was produced by Dr. M.J. Woo, now a National Research Council fellow at Lewis, and the G-VIS laboratory at Lewis. This video shows the behavior of supersonic shocks produced by pistons in enclosed cylinders by following exactly the behavior of thousands of particles. The major assumptions made were that the particles involved were hard spheres and that all collisions with the walls and with other particles were fully elastic. The animated video was voted one of two
Benchmark calculations of power distribution within assemblies
International Nuclear Information System (INIS)
The main objective of this Benchmark is to compare different techniques for fine flux prediction based upon coarse mesh diffusion or transport calculations. We proposed 5 ''core'' configurations including different assembly types (17 x 17 pins, ''uranium'', ''absorber'' or ''MOX'' assemblies), with different boundary conditions. The specification required results in terms of reactivity, pin by pin fluxes and production rate distributions. The proposal for these Benchmark calculations was made by J.C. LEFEBVRE, J. MONDOT, J.P. WEST and the specification (with nuclear data, assembly types, core configurations for 2D geometry and results presentation) was distributed to correspondents of the OECD Nuclear Energy Agency. 11 countries and 19 companies answered the exercise proposed by this Benchmark. Heterogeneous calculations and homogeneous calculations were made. Various methods were used to produce the results: diffusion (finite differences, nodal...), transport (Pij, Sn, Monte Carlo). This report presents an analysis and intercomparisons of all the results received
A novel algorithmic method for piezoresistance calculation
International Nuclear Information System (INIS)
A novel algorithmic method, based on the different stress distribution on the surface of thin film in an SOI microstructure, is put forward to calculate the value of the silicon piezoresistance on the sensitive film. In the proposed method, we take the Ritz method as an initial theoretical model to calculate the rate of piezoresistance ΔR/R through an integral (the closed area Ω where the surface piezoresistance of the film lies as the integral area and the product of stress σ and piezoresistive coefficient π as the integral object) and compare the theoretical values with the experimental results. Compared with the traditional method, this novel calculation method is more accurate when applied to calculating the value of the silicon piezoresistance on the sensitive film of an SOI pieoresistive pressure sensor. (semiconductor devices)
Calculation of eigenfunction fluxes in nuclear systems
International Nuclear Information System (INIS)
A new Monte Carlo method is being developed to calculate eigenfunction fluxes in critical or near-critical nuclear systems. The correct estimation of fluxes is essential for radiation protection and shielding near these systems, in addition to isotope production, isotope depletion, nuclear criticality and other applications. The proposed method applies to Monte Carlo criticality eigenvalue calculations in which the fission sites in one generation are used as fission sources in subsequent generations. The usual Monte Carlo power iteration method for such problems often calculates fluxes (eigenfunctions) that are inaccurate and very different in symmetric parts of a problem geometry. The proposed method calculates flux distributions by estimating an approximate fission matrix. The way the fission matrix is estimated and used differs from other recent works. Preliminary results are promising. (authors)
International Nuclear Information System (INIS)
Thin natCr targets were obtained by electroplating, using 23.75 μm Cu foils as backings. In five stacked foil irradiations, followed by high resolution gamma spectroscopy, the cross sections for production of 52gFe, 49,51cumCr, 52cum,54,56cumMn and 48cumV in Cr and 61Cu,68Ga in Cu were measured up to 39 MeV incident α-particle energy. Reduced uncertainty is obtained by simultaneous remeasurement of the natCu(α,x)67,66Ga monitor reactions over the whole energy range. Comparisons with the scarce literature values and results from the TENDL-2013 on-line library, based on the theoretical code family TALYS-1.6, were made. A discussion of the production routes for 52gFe with achievable yields and contamination rates was made
ORIC central region calculations
International Nuclear Information System (INIS)
The central region for the K = 100 Oak Ridge Isochronous Cyclotron, ORIC, will be modified to provide better orbit centering, focusing of orbits in the axial direction, and phase selection, in order to improve extraction efficiency, and reduce radioactive activation of cyclotron components. The central region is specifically designed for the acceleration of intense light ion beams such as 60 MeV protons and 15--100 MeV alphas. These beams will be used in the production of radioactive atoms in the Radioactive Ion Beam Project at Oak Ridge National Laboratory
Sarria Morales, Marina
2013-01-01
This master’s thesis can be characterized as a research project about nuclear engineering. The object of this thesis is the primary system of Vandellós II nuclear power plant. Specifically, it has been focused on the dynamic behavior of corrosion products in the nuclear fuel of a nuclear core Vandellós II PWR. The report describes the operation of the Reactor Coolant System (RCS), highlighting and making a detailed study of an existing and common problem in different nuclear plants a...
Exoplanet Equilibrium Chemistry Calculations
Blumenthal, Sarah; Harrington, J.; Bowman, M.; Blecic, J.
2013-10-01
Recently, Agundez et al. (2012, A&A 548, A73) used a chemical kinetics code to study a model HD 209458b (equilibrium temperature of 1450 K, assuming full redistribution and 0 albedo). They found that thermochemistry dominates most of the dayside, but that significant compositional gradients may exist across the dayside. We calculate equilibrium-chemistry molecular abundances for several model exoplanets, using NASA's open-source Chemical Equilibrium Abundances code (McBride and Gordon 1996). We vary the degree of radiation redistribution to the dark side, ranging from total redistribution to instantaneous reradiation. Atomically, both the solar abundance multiple and the carbon fraction vary. Planet substellar temperatures range from just above 1200 K, where photochemistry should no longer be important, to those of hot planets (3000 K). We present synthetic abundance images for the key spectroscopic molecules CO, CH4, and H2O for several hot-Jupiter model planets. This work was supported by the NASA Planetary Atmospheres grant NNX12AI69G.
Relative Hazard Calculation Methodology
International Nuclear Information System (INIS)
The methodology presented in this document was developed to provide a means of calculating the RH ratios to use in developing useful graphic illustrations. The RH equation, as presented in this methodology, is primarily a collection of key factors relevant to understanding the hazards and risks associated with projected risk management activities. The RH equation has the potential for much broader application than generating risk profiles. For example, it can be used to compare one risk management activity with another, instead of just comparing it to a fixed baseline as was done for the risk profiles. If the appropriate source term data are available, it could be used in its non-ratio form to estimate absolute values of the associated hazards. These estimated values of hazard could then be examined to help understand which risk management activities are addressing the higher hazard conditions at a site. Graphics could be generated from these absolute hazard values to compare high-hazard conditions. If the RH equation is used in this manner, care must be taken to specifically define and qualify the estimated absolute hazard values (e.g., identify which factors were considered and which ones tended to drive the hazard estimation)
Configuration space Faddeev calculations
International Nuclear Information System (INIS)
The detailed study of few-body systems provides one of the most precise tools for studying the dynamics of nuclei. Our research program consists of a careful theoretical study of the nuclear few-body systems. During the past year we have completed several aspects of this program. We have continued our program of using the trinucleon system to investigate the validity of various realistic nucleon-nucleon potentials. Also, the effects of meson-exchange currents in nuclear systems have been studied. Initial calculations using the configuration-space Faddeev equations for nucleon-deuteron scattering have been completed. With modifications to treat relativistic systems, few-body methods can be applied to phenomena that are sensitive to the structure of the individual hadrons. We have completed a review of Relativistic Hamiltonian Dynamics in Nuclear and Particle Physics for Advances in Nuclear Physics. Although it is called a review, it is a large document that contains a significant amount of new research
International Nuclear Information System (INIS)
One of the most important aspects in relation to the quality assurance in any analytical activity is the estimation of measurement uncertainty. There is general agreement that 'the expression of the result of a measurement is not complete without specifying its associated uncertainty'. An analytical process is the mechanism for obtaining methodological information (measurand) of a material system (population). This implies the need for the definition of the problem, the choice of methods for sampling and measurement and proper execution of these activities for obtaining information. The result of a measurement is only an approximation or estimate of the value of the measurand, which is complete only when accompanied by an estimate of the uncertainty of the analytical process. According to the 'Vocabulary of Basic and General Terms in Metrology' measurement uncertainty' is the parameter associated with the result of a measurement that characterizes the dispersion of the values that could reasonably be attributed to the measurand (or magnitude). This parameter could be a standard deviation or a confidence interval. The uncertainty evaluation requires detailed look at all possible sources, but not disproportionately. We can make a good estimate of the uncertainty concentrating efforts on the largest contributions. The key steps of the process of determining the uncertainty in the measurements are: - the specification of the measurand; - identification of the sources of uncertainty - the quantification of individual components of uncertainty, - calculate the combined standard uncertainty; - report of uncertainty.
Relativistic few body calculations
International Nuclear Information System (INIS)
A modern treatment of the nuclear few-body problem must take into account both the quark structure of baryons and mesons, which should be important at short range, and the relativistic exchange of mesons, which describes the long range, peripheral interactions. A way to model both of these aspects is described. The long range, peripheral interactions are calculated using the spectator model, a general approach in which the spectators to nucleon interactions are put on their mass-shell. Recent numerical results for a relativistic OBE model of the NN interaction, obtained by solving a relativistic equation with one-particle on mass-shell, will be presented and discussed. Two meson exchange models, one with only four mesons (π,σ,/rho/,ω) but with a 25% admixture of γ5 coupling for the pion, and a second with six mesons (π,σ,/rho/,ω,δ,/eta/) but pure γ5γ/sup μ/ pion coupling, are shown to give very good quantitative fits to the NN scattering phase shifts below 400 MeV, and also a good description of the /rvec p/ 40Ca elastic scattering observables. Applications of this model to electromagnetic interactions of the two body system, with emphasis on the determination of relativistic current operators consistent with the dynamics and the exact treatment of current conservation in the presence of phenomenological form factors, will be described. 18 refs., 8 figs
Energy Technology Data Exchange (ETDEWEB)
Hermanne, A.; Adam Rebeles, R. [Cyclotron Laboratory, Vrije Universiteit Brussel, Brussel 1090 (Belgium); Tárkányi, F.; Takács, S. [Institute of Nuclear Research, Hungarian Academy of Science, 4026 Debrecen (Hungary)
2015-08-01
Thin {sup nat}Cr targets were obtained by electroplating, using 23.75 μm Cu foils as backings. In five stacked foil irradiations, followed by high resolution gamma spectroscopy, the cross sections for production of {sup 52g}Fe, {sup 49,51cum}Cr, {sup 52cum,54,56cum}Mn and {sup 48cum}V in Cr and {sup 61}Cu,{sup 68}Ga in Cu were measured up to 39 MeV incident α-particle energy. Reduced uncertainty is obtained by simultaneous remeasurement of the {sup nat}Cu(α,x){sup 67,66}Ga monitor reactions over the whole energy range. Comparisons with the scarce literature values and results from the TENDL-2013 on-line library, based on the theoretical code family TALYS-1.6, were made. A discussion of the production routes for {sup 52g}Fe with achievable yields and contamination rates was made.
Energy Technology Data Exchange (ETDEWEB)
Lyng, Kari-Anne; Modahl, Ingunn Saur; Morken, John; Briseid, Tormod; Vold, Bjoern Ivar; Hanssen, Ole Joergen; Soerby, Ivar
2011-07-01
The main objective of the project was to develop a climate model and an economy model for the entire value-chain from collection and biogas production for the treatment of digestate, which should contribute to increase production of biogas in Norway by an efficient and climate proper utilization of fertilizers and waste. The models are defined in a number of parameter values for each of the different substrates and for each life-cycle stage of the value chain. By changing parameter values enables the analysis models in different regions, with flexible solutions for local differences. This may be options for the location of plants in relation to transport needs, size of plants in relation to efficiency and amount of substrate, utilization of biogas and digestate and what type of energy that can be replaced by biogas (eg fuel for vehicles, heating, electricity) and digestate (fertilizer and soil conditioner product). This report presents the defined parameters in the model, the basic values that are added to the table, results for basic value, as well as results from testing of the model for biogas production in Vestfold and Oestfold. Results:The analysis performed shows that the models are suitable to identify where in the value chain, the major climate impacts occur where the greatest costs are incurred, what is contributing to a reduction in greenhouse gas emissions and income, and how it can be most effective to take action or to motivate to technology. Analyses of biogas production from manure and food waste results in the following robust conclusions when viewing the biogas production in a greenhouse gas perspective: Biogas is a good initiative for the treatment of food waste and manure in a climate perspective. Of the analyzed scenarios, the results show that biogas which will be upgraded to fuel quality and diesel substitutes provide the greatest climate benefits. It is beneficial to mix substrates. The largest contribution of greenhouse gases are nitrous
Progress in target physics and design for heavy ion fusion
International Nuclear Information System (INIS)
Two-dimensional, integrated calculations of a close-coupled version of the distributed radiator, heavy ion target predict gain 130 from 3.3 MJ of beam energy. To achieve these results, the case-to-capsule ratio was decreased by about 25% from the previous heavy ion targets [M. Tabak and D. Callahan-Miller, Phys. Plasmas 5, 1895 (1998)]. These targets are robust to changes in the ion stopping model because changes in the ion stopping model can be accommodated by changes to the target. The capsule is also insensitive to changes in the deuterium-tritium (DT) gas fill in the center of the capsule over the range that is of interest for target fabrication and target injection. Single-mode Rayleigh-Taylor growth rates for this capsule are smaller than those for at least one National Ignition Facility (NIF) [J. A. Paisner et al., Laser Focus World 30, 75 (1994)] design. As a result, stability issues for the heavy ion capsule can be settled on NIF. The close-coupled target also opens up the possibility of a high gain engineering test facility from a 1.5-2 MJ driver; calculations predict that gain 90 is achievable from 1.75 MJ of beam energy. Finally, the choice of hohlraum wall material, which must satisfy constraints from target physics, environment and safety, chamber design, and target fabrication, is discussed. (c) 2000 American Institute of Physics
The rating reliability calculator
Directory of Open Access Journals (Sweden)
Solomon David J
2004-04-01
Full Text Available Abstract Background Rating scales form an important means of gathering evaluation data. Since important decisions are often based on these evaluations, determining the reliability of rating data can be critical. Most commonly used methods of estimating reliability require a complete set of ratings i.e. every subject being rated must be rated by each judge. Over fifty years ago Ebel described an algorithm for estimating the reliability of ratings based on incomplete data. While his article has been widely cited over the years, software based on the algorithm is not readily available. This paper describes an easy-to-use Web-based utility for estimating the reliability of ratings based on incomplete data using Ebel's algorithm. Methods The program is available public use on our server and the source code is freely available under GNU General Public License. The utility is written in PHP, a common open source imbedded scripting language. The rating data can be entered in a convenient format on the user's personal computer that the program will upload to the server for calculating the reliability and other statistics describing the ratings. Results When the program is run it displays the reliability, number of subject rated, harmonic mean number of judges rating each subject, the mean and standard deviation of the averaged ratings per subject. The program also displays the mean, standard deviation and number of ratings for each subject rated. Additionally the program will estimate the reliability of an average of a number of ratings for each subject via the Spearman-Brown prophecy formula. Conclusion This simple web-based program provides a convenient means of estimating the reliability of rating data without the need to conduct special studies in order to provide complete rating data. I would welcome other researchers revising and enhancing the program.
Surface retention capacity calculation
David, Vaclav; Dostal, Tomas
2010-05-01
Flood wave transformation in the floodplain is the phenomenon which is researched within interdisciplinary project NIVA - Water Retention in Floodplains and Possibilities of Retention Capacity Increase. The project focuses on broad range of floodplain ecosystem services and mitigation of flooding is one of them. Despite main influence on flood wave transformation is due to flow retardation, retention in surface depressions within floodplain has been analyzed to get better overview of whole transformation process. Detail digital relief model (DRM) has been used for given purposes to be able to analyze terrain depressions volumes. The model was developed with use of stereophotogrammetric evaluation of airborne images with high resolution of 10 cm. It was essential for purposes of presented analysis not to apply pit removal routines which are often used for generation of DRM for hydrological modelling purposes. First, the methodology of analysis was prepared and tested on artificial surface. This surface was created using random raster generation, filtration and resampling with final resolution of 1000 x 1000 units and height of maximum 10 units above datum. The methodology itself is based on analysis of areas inundated by water at different elevation levels. Volume is than calculated for each depression using extraction of terrain elevations under corresponding water level. The method was then applied on the area of Lužnice River floodplain section to assess retention capacity of real floodplain. The floodplain had to be cut into sections perpendicular to main river orientation for analyses as the method was tested for square shaped area without any significant inclination. Results obtained by mentioned analysis are presented in this paper. Acknowledgement Presented research was accomplished within national project NIVA - Water Retention in Floodplains and Possibilities of Retention Capacity Increase, nr. QH82078. The project is funded by Ministry of Agriculture of
Energy Technology Data Exchange (ETDEWEB)
Vargas Cuervo, Carlos Hernan
1997-03-01
The main objective of this work is to develop a methodology to optimize the simultaneous computation of two parameters in the process of production history matching. This work describes a procedure to minimize an objective function established to find the values of the parameters which are modified in the process. The parameters are chosen after a sensibility analysis. Two optimization methods are tested: a Region Search Method (MBR) and Polytope Method. Both are based in direct search methods which do not require the function derivative. The software PVM (Parallel Virtual Machine) is used to parallelize the simulation runs, allowing the acceleration of the process and the search of multiple solutions. The validation of the methodology is applied to two reservoir models: one homogeneous and other heterogeneous. The advantages of each method and of the parallelization are also present. (author)
Cost calculation in agricultural enterprises in theory and practice
Directory of Open Access Journals (Sweden)
Wojciech Ziętara
2009-01-01
Full Text Available The article is dedicated to evolution of the production costs calculation theory in agriculture from the second half of XVIII century till present times. The author emphasized long lasting dispute among the economists about usefulness of the full account of unit costs of production in evaluation of production profitability. Moreover, utility of the part-costs account in evaluation of production competitiveness, as well as their value in evaluation of the production processes and structure (using optimisation methods was analysed. Additionally article describes current problems of cost calculation in agriculture.
COST MEASUREMENT AND COST MANAGEMENT IN TARGET COSTING
Moisello Anna Maria
2012-01-01
Firms are coping with a competitive scenario characterized by quick changes produced by internationalization, concentration, restructuring, technological innovation processes and financial market crisis. On the one hand market enlargement have increased the number and the segmentation of customers and have raised the number of competitors, on the other hand technological innovation has reduced product life cycle. So firms have to adjust their management models to this scenario, pursuing custo...
40 CFR 98.223 - Calculating GHG emissions.
2010-07-01
... (CONTINUED) MANDATORY GREENHOUSE GAS REPORTING Nitric Acid Production § 98.223 Calculating GHG emissions. (a... nitric acid train “t” (fraction of annual production that abatement technology is operating). Pa t = Total annual nitric acid production from nitric acid train “t” (ton acid produced, 100 percent...
40 CFR 98.403 - Calculating GHG emissions.
2010-07-01
... part, calculate the estimated CO2 emissions that would result from the complete combustion or oxidation... CO2 emissions that would result from the complete combustion or oxidation of the product received at... result from the complete combustion or oxidation of the product(s) supplied using Equation NN-2 of...
Calculation of multiphoton ionization processes
Chang, T. N.; Poe, R. T.
1976-01-01
We propose an accurate and efficient procedure in the calculation of multiphoton ionization processes. In addition to the calculational advantage, this procedure also enables us to study the relative contributions of the resonant and nonresonant intermediate states.
HEU benchmark calculations and LEU preliminary calculations for IRR-1
International Nuclear Information System (INIS)
We performed neutronics calculations for the Soreq Research Reactor, IRR-1. The calculations were done for the purpose of upgrading and benchmarking our codes and methods. The codes used were mainly WIMS-D/4 for cell calculations and the three dimensional diffusion code CITATION for full core calculations. The experimental flux was obtained by gold wire activation methods and compared with our calculated flux profile. The IRR-1 is loaded with highly enriched uranium fuel assemblies, of the plate type. In the framework of preparation for conversion to low enrichment fuel, additional calculations were done assuming the presence of LEU fresh fuel. In these preliminary calculations we investigated the effect on the criticality and flux distributions of the increase of U-238 loading, and the corresponding uranium density.(author)
RTU Comparison Calculator Enhancement Plan
Energy Technology Data Exchange (ETDEWEB)
Miller, James D.; Wang, Weimin; Katipamula, Srinivas
2014-03-31
Over the past two years, Department of Energy’s Building Technologies Office (BTO) has been investigating ways to increase the operating efficiency of the packaged rooftop units (RTUs) in the field. First, by issuing a challenge to the RTU manufactures to increase the integrated energy efficiency ratio (IEER) by 60% over the existing ASHRAE 90.1-2010 standard. Second, by evaluating the performance of an advanced RTU controller that reduces the energy consumption by over 40%. BTO has previously also funded development of a RTU comparison calculator (RTUCC). RTUCC is a web-based tool that provides the user a way to compare energy and cost savings for two units with different efficiencies. However, the RTUCC currently cannot compare savings associated with either the RTU Challenge unit or the advanced RTU controls retrofit. Therefore, BTO has asked PNNL to enhance the tool so building owners can compare energy and savings associated with this new class of products. This document provides the details of the enhancements that are required to support estimating energy savings from use of RTU challenge units or advanced controls on existing RTUs.
RTU Comparison Calculator Enhancement Plan
Energy Technology Data Exchange (ETDEWEB)
Miller, James D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wang, Weimin [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Katipamula, Srinivas [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
2015-07-01
Over the past two years, Department of Energy’s Building Technologies Office (BTO) has been investigating ways to increase the operating efficiency of the packaged rooftop units (RTUs) in the field. First, by issuing a challenge to the RTU manufactures to increase the integrated energy efficiency ratio (IEER) by 60% over the existing ASHRAE 90.1-2010 standard. Second, by evaluating the performance of an advanced RTU controller that reduces the energy consumption by over 40%. BTO has previously also funded development of a RTU comparison calculator (RTUCC). RTUCC is a web-based tool that provides the user a way to compare energy and cost savings for two units with different efficiencies. However, the RTUCC currently cannot compare savings associated with either the RTU Challenge unit or the advanced RTU controls retrofit. Therefore, BTO has asked PNNL to enhance the tool so building owners can compare energy and savings associated with this new class of products. This document provides the details of the enhancements that are required to support estimating energy savings from use of RTU challenge units or advanced controls on existing RTUs.
Activity calculation of radioisotopes in HFETR
International Nuclear Information System (INIS)
The activity calculating method and formulas of seven kinds of radioisotopes for High Flux Engineering Test REactor (HFETR) are given. The perturbation of targets to neutron fluence rate is considered while targets are put into the neutron fluence rate field of reactor core. All perturbing factors of seven kinds of radioisotopes being used in HFETR are presented. After considering the perturbation, the calculating accuracy of radioisotope activity has been raised 10%. The given method and formulas have ended the history of all activities estimated by experiences, except for that of 60Co, in the radioisotope production of HFETR. The conclusions are also useful and instructive for the production of radioisotopes in HFETR. (8 tabs.)
One-loop calculations with massive particles
International Nuclear Information System (INIS)
In this thesis some techniques for performing one-loop calculations with massive particles are presented. Numerical techniques are presented necessary for evaluating one-loop integrals which occur in one-loop calculations of photon-photon scattering. The algorithms have been coded in FORTRAN (to evaluate the scalar integrals) and the algebraic language FORM (to reduce the tensor integrals to scalar integrals). Applications are made in the theory of the strong interaction, QCD, i.e. in handling one-loop integrals with massive particles, in order to regulate the infinities by mass parameters encountered in this theory. However this simplifies the computation considerably, the description of the proton structure functions have to be renormalized in order to obtain physical results. This renormalization is different from the published results for the gluon and thus has to be redone. The first physics results that have been obtained with these new methods are presented. These concern heavy quark production in semi-leptonic interactions, for instance neutrino charm production and top production at the electron-proton (ep) collider HERA and the proposed LEP/LHC combination. Total and differential cross-sections for one-loop corrections to top production at the HERA and proposed LEP/HLC ep colliders are given and structure functions for charmed quark production are compared with previously published results. (author). 58 refs.; 18 figs.; 5 tabs
Monte Carlo dose calculations for dynamic IMRT treatments
International Nuclear Information System (INIS)
Dose calculations for intensity modulated radiation therapy (IMRT) face new challenges due to the complex leaf geometry and time dependent nature of the delivery. A fast method of particle transport through a dynamic multileaf collimator (MLC) geometry that accounts for photon attenuation and first-scattered Compton photon production has been incorporated into an existing Monte Carlo code used for patient dose calculations. Dosimetric agreement between calculation and measurement for two photon energies and MLC types is within experimental error for the sliding window tests. For a patient IMRT field, the Monte Carlo calculations are closer to measured dose than similar superposition or pencil beam calculations. (author)
A comparison of carbon calculators
International Nuclear Information System (INIS)
International attention to carbon dioxide emissions is turning to an individual's contribution, or 'carbon footprint.' Calculators that estimate an individual's CO2 emissions have become more prevalent on the internet. Even with similar inputs, however, these calculators can generate varying results, often by as much as several metric tons per annum per individual activity. This paper examines the similarities and differences among ten US-based calculators. Overall, the calculators lack consistency, especially for estimates of CO2 emissions from household electricity consumption. In addition, most calculators lack information about their methods and estimates, which impedes comparison and validation. Although carbon calculators can promote public awareness of carbon emissions from individual behavior, this paper reveals the need for improved consistency and transparency in the calculators
Carbon footprint calculators for public procurement
Mattinen, Maija; Nissinen, Ari
2011-01-01
There is growing interest in public organizations to take into account the climate impacts of the products and services they procure. Furthermore, in Finland a Government ResolutionÂ exists that provides a framework and sets aims for sustainable public procurement. Several municipalities in the Helsinki region together with the Helsinki Region Environmental Services Authority and several expert organizations initiated an EU Life project, JULIA2030, to develop calculators for different sec...
Automation of 2-loop Amplitude Calculations
Jones, S P
2016-01-01
Some of the tools and techniques that have recently been used to compute Higgs boson pair production at NLO in QCD are discussed. The calculation relies on the use of integral reduction, to reduce the number of integrals which must be computed, and expressing the amplitude in terms of a quasi-finite basis, which simplifies their numeric evaluation. Emphasis is placed on sector decomposition and Quasi-Monte Carlo (QMC) integration which are used to numerically compute the master integrals.
International Nuclear Information System (INIS)
The kerma heat production density, tritum production density, and dose in a lithium-fluoride pile with a deuterium-tritum neutron source were calculated with a data processing code, UFO, from the pulse height distribution of a miniature NE213 neutron spectrometer, and compared with the values calculated with a Monte Carlo code, MORSE-CV. Both the UFO and MORSE-CV values agreed with the statistical error (less than 6%) of the MORSE-CV calculations, except for the outer-most point in the pile. The MORSE-CV values were slightly smaller than the UFO values for almost all cases, and this tendency increased with increasing distance from the neutron source
REVIEW OF METHODOLOGIES FOR COSTS CALCULATING OF RUMINANTS IN SLOVAKIA
Directory of Open Access Journals (Sweden)
Zuzana KRUPOVÁ
2012-09-01
Full Text Available The objective of this work was to synthesise and analyse the methodologies and the biological aspects of the costs calculation in ruminants in Slovakia. According to literature, the account classification of cost items is most often considered for construction of costing formula. The costs are mostly divided into fixed (costs independent from volume of herd’s production and variable ones (costs connected with improvement of breeding conditions. Cost for feeds and beddings, labour costs, other direct costs and depreciations were found as the most important cost items in ruminants. It can be assumed that including the depreciations into costs of the basic herd takes into consideration the real costs simultaneously invested into raising of young animals in the given period. Costs are calculated for the unit of the main and by-products and their classification is influenced mainly by the type of livestock and production system. In dairy cows is usually milk defined as the main product, and by- products are live born calf and manure. The base calculation unit is kilogram of milk (basic herd of cows and kilogram of gain and kilogram of live weight (young breeding cattle. In suckler cows is a live-born calf the main product and manure is the by-product. The costs are mostly calculated per suckler cow, live-born calf and per kilogram of live weight of weaned calf. Similar division of products into main and by-products is also in cost calculation for sheep categories. The difference is that clotted cheese is also considered as the main product of basic herd in dairy sheep and greasy wool as the by-products in all categories. Definition of the base calculation units in sheep categories followed the mentioned classification. The value of a by-product in cattle and sheep is usually set according to its quantity and intra- plant price of the by-product. In the calculation of the costs for sheep and cattle the “structural ewe” and “structural cow
Invert Effective Thermal Conductivity Calculation
International Nuclear Information System (INIS)
The objective of this calculation is to evaluate the temperature-dependent effective thermal conductivities of a repository-emplaced invert steel set and surrounding ballast material. The scope of this calculation analyzes a ballast-material thermal conductivity range of 0.10 to 0.70 W/m · K, a transverse beam spacing range of 0.75 to 1.50 meters, and beam compositions of A 516 carbon steel and plain carbon steel. Results from this calculation are intended to support calculations that identify waste package and repository thermal characteristics for Site Recommendation (SR). This calculation was developed by Waste Package Department (WPD) under Office of Civilian Radioactive Waste Management (OCRWM) procedure AP-3.12Q, Revision 1, ICN 0, Calculations
Global nuclear-structure calculations
International Nuclear Information System (INIS)
The revival of interest in nuclear ground-state octupole deformations that occurred in the 1980's was stimulated by observations in 1980 of particularly large deviations between calculated and experimental masses in the Ra region, in a global calculation of nuclear ground-state masses. By minimizing the total potential energy with respect to octupole shape degrees of freedom in addition to ε2 and ε4 used originally, a vastly improved agreement between calculated and experimental masses was obtained. To study the global behavior and interrelationships between other nuclear properties, we calculate nuclear ground-state masses, spins, pairing gaps and Β-decay and half-lives and compare the results to experimental qualities. The calculations are based on the macroscopic-microscopic approach, with the microscopic contributions calculated in a folded-Yukawa single-particle potential
Measurement and calculation of evaporation
Plesničar, Leja
2015-01-01
The thesis presents three selected methods of measurement and calculation of the evapotranspiration on research plot at Hajdrihova 28 in Ljubljana. First method is measurement by evaporation pan type A and the other two methods are empirical equations for potential evapotranspiration calculation: FAO Penman-Monteith equation and Thornthwait equation. The results obtained for all three methods are compared with each other. Calculated results according to the FAO Penman-Monteith equation wer...
Calculation of Spectra of Solids:
DEFF Research Database (Denmark)
Lindgård, Per-Anker
1975-01-01
The Gilat-Raubenheimer method simplified to tetrahedron division is used to calculate the real and imaginary part of the dynamical response function for electrons. A frequency expansion for the real part is discussed. The Lindhard function is calculated as a test for numerical accuracy....... The conduction electron susceptibility is calculated for Gd, Tb and Dy using the RAPW energy bands by Keeton and Louks....
39 CFR 3010.21 - Calculation of annual limitation.
2010-07-01
... 39 Postal Service 1 2010-07-01 2010-07-01 false Calculation of annual limitation. 3010.21 Section 3010.21 Postal Service POSTAL REGULATORY COMMISSION PERSONNEL REGULATION OF RATES FOR MARKET DOMINANT PRODUCTS Rules for Applying the Price Cap § 3010.21 Calculation of annual limitation. (a) The...
CAVEAT calculations of shock interactions
International Nuclear Information System (INIS)
CAVEAT is a computer code for calculating the time-varying fluid dynamics of several adjacent materials in two or three space dimensions. Using an extended Godunov technique and adaptive meshing, the code allows for large slippage at material interfaces. To exhibit the capability for calculating strong distortions we have performed a variety of calculations describing the interaction of shocks with rigid wedges, cylinders, and spheres and deformable cylindrical, spherical, and conical shells in two space dimensions. Comparison of the results with experimental data and analytical solutions demonstrates the considerable accuracy that can be expected from calculations with this code
Optimization of sources for focusing wave energy in targeted formations
Jeong, C
2010-06-08
We discuss a numerical approach for identifying the surface excitation that is necessary to maximize the response of a targeted subsurface formation. The motivation stems from observations in the aftermath of earthquakes, and from limited field experiments, whereby increased oil production rates were recorded and were solely attributable to the induced reservoir shaking. The observations suggest that focusing wave energy to the reservoir could serve as an effective low-cost enhanced oil recovery method. In this paper, we report on a general method that allows the determination of the source excitation, when provided with a desired maximization outcome at the targeted formation. We discuss, for example, how to construct the excitation that will maximize the kinetic energy in the target zone, while keeping silent the neighbouring zones. To this end, we cast the problem as an inverse-source problem, and use a partial-differential- equation-constrained optimization approach to arrive at an optimized source signal. We seek to satisfy stationarity of an augmented functional, which formally leads to a triplet of state, adjoint and control problems. We use finite elements to resolve the state and adjoint problems, and an iterative scheme to satisfy the control problem to converge to the sought source signal. We report on one-dimensional numerical experiments in the time domain involving a layered medium of semi-infinite extent. The numerical results show that the targeted formation\\'s kinetic energy resulting from an optimized wave source could be several times greater than the one resulting from a blind source choice, and could overcome the mobility threshold of entrapped reservoir oil. © 2010 Nanjing Geophysical Research Institute.
Optimization of sources for focusing wave energy in targeted formations
International Nuclear Information System (INIS)
We discuss a numerical approach for identifying the surface excitation that is necessary to maximize the response of a targeted subsurface formation. The motivation stems from observations in the aftermath of earthquakes, and from limited field experiments, whereby increased oil production rates were recorded and were solely attributable to the induced reservoir shaking. The observations suggest that focusing wave energy to the reservoir could serve as an effective low-cost enhanced oil recovery method. In this paper, we report on a general method that allows the determination of the source excitation, when provided with a desired maximization outcome at the targeted formation. We discuss, for example, how to construct the excitation that will maximize the kinetic energy in the target zone, while keeping silent the neighbouring zones. To this end, we cast the problem as an inverse-source problem, and use a partial-differential-equation-constrained optimization approach to arrive at an optimized source signal. We seek to satisfy stationarity of an augmented functional, which formally leads to a triplet of state, adjoint and control problems. We use finite elements to resolve the state and adjoint problems, and an iterative scheme to satisfy the control problem to converge to the sought source signal. We report on one-dimensional numerical experiments in the time domain involving a layered medium of semi-infinite extent. The numerical results show that the targeted formation's kinetic energy resulting from an optimized wave source could be several times greater than the one resulting from a blind source choice, and could overcome the mobility threshold of entrapped reservoir oil
COSTS CALCULATION OF TARGET COSTING METHOD
Directory of Open Access Journals (Sweden)
Sebastian UNGUREANU
2014-06-01
Full Text Available Cost information system plays an important role in every organization in the decision making process. An important task of management is ensuring control of the operations, processes, sectors, and not ultimately on costs. Although in achieving the objectives of an organization compete more control systems (production control, quality control, etc., the cost information system is important because monitors results of the other. Detailed analysis of costs, production cost calculation, quantification of losses, estimate the work efficiency provides a solid basis for financial control. Knowledge of the costs is a decisive factor in taking decisions and planning future activities. Managers are concerned about the costs that will appear in the future, their level underpinning the supply and production decisions as well as price policy. An important factor is the efficiency of cost information system in such a way that the information provided by it may be useful for decisions and planning of the work.
Calculations of effective atomic number
Energy Technology Data Exchange (ETDEWEB)
Kaliman, Z. [Department of Physics, Faculty of Arts and Sciences, Omladinska 14, Rijeka (Croatia); Orlic, N. [Department of Physics, Faculty of Arts and Sciences, Omladinska 14, Rijeka (Croatia)], E-mail: norlic@ffri.hr; Jelovica, I. [Department of Physics, Faculty of Arts and Sciences, Omladinska 14, Rijeka (Croatia)
2007-09-21
We present and discuss effective atomic number (Z{sub eff}) obtained by different methods of calculations. There is no unique relation between the computed values. This observation led us to the conclusion that any Z{sub eff} is valid only for given process. We illustrate calculations for different subshells of atom Z=72 and for M3 subshell of several other atoms.
Calculation of two Belyi pairs
Dremov, V. A.
2008-01-01
We calculate two Belyi pairs using the properties of Mulase-Penkava differential. Details are provided including accurate construction of coordinates, variables and equations. The calculation is a part of the work which results in a catalogue arXiv:0710.2658
CALCULATION OF COMPANY COSTS THROUGH THE DIRECT-COSTING CALCULATION METHOD
Directory of Open Access Journals (Sweden)
Florin-Constantin DIMA
2013-06-01
Full Text Available The cost of production has as its starting point the purchase cost of raw materials and consumables, as well as their processing cost and the calculation of the production cost involves complex aspects. This article is based on the two major concepts of costs calculation, namely the concept of full costs and the concept of partial costs, and it analyses the direct-costing calculation method. Necessity of the Development of calculation methods to ensure rapid determination of the cost of production, and the establishment of indicators broad spectrum of information necessary for making decisions to streamline a business activity conducted by direct-costing method. Direct-costing method appeared in the U.S. for the first time in 1934 (applied by Jonathan Harris and G. Charter Harrison. Subsequently, this method was applied to European countries (England, France, Germany etc.. We stopped on this method because it is considered a modern method of costing. Therefore, we analyzed both advantages and limitations of the method in question
Shielding calculational system for plutonium
International Nuclear Information System (INIS)
A computer calculational system has been developed and assembled specifically for calculating dose rates in AEC plutonium fabrication facilities. The system consists of two computer codes and all nuclear data necessary for calculation of neutron and gamma dose rates from plutonium. The codes include the multigroup version of the Battelle Monte Carlo code for solution of general neutron and gamma shielding problems and the PUSHLD code for solution of shielding problems where low energy gamma and x-rays are important. The nuclear data consists of built in neutron and gamma yields and spectra for various plutonium compounds, an automatic calculation of age effects and all cross-sections commonly used. Experimental correlations have been performed to verify portions of the calculational system. (23 tables, 7 figs, 16 refs) (U.S.)
Willow growing - Methods of calculation and profitability
International Nuclear Information System (INIS)
The calculation method presented here makes it possible to conduct profitability comparisons between annual and perennial crops and in addition take the planning situation into account. The method applied is a modified total step calculation. The difference between a traditional total step calculation and the modified version is the way in which payments and disbursements are taken into account over a period of several years. This is achieved by combining the present value method and the annuity method. The choice of interest rate has great bearing on the result in perennial calculations. The various components influencing the interest rate are analysed and factors relating to the establishment of the interest rate in different situations are described. The risk factor can be an important variable component of the interest rate calculation. Risk is also addressed from an approach in accordance with portfolio theory. The application of the methods sheds light on the profitability of Salix cultivation from the viewpoint of business economics, and also how different factors influence the profitability of Salix cultivation. Aspects studied are harvesting intervals, the importance of yield level, the competitiveness of Salix versus grain cultivation, the influence of income taxes on profitability etc. Methods for evaluation of activities concerning cultivation of a perennial crop are described and also involve the application of nitrogen fertilization to Salix cultivation. Studies have been performed using these methods to look into nitrogen fertilizer profitability in Salix cultivation during the first rotation period. Nitrogen fertilizer profitability has been investigated involving both production functions and cost calculations, taking the year fertilization into consideration. 72 refs., 2 figs., 52 tabs
Closure and Sealing Design Calculation
Energy Technology Data Exchange (ETDEWEB)
T. Lahnalampi; J. Case
2005-08-26
The purpose of the ''Closure and Sealing Design Calculation'' is to illustrate closure and sealing methods for sealing shafts, ramps, and identify boreholes that require sealing in order to limit the potential of water infiltration. In addition, this calculation will provide a description of the magma that can reduce the consequences of an igneous event intersecting the repository. This calculation will also include a listing of the project requirements related to closure and sealing. The scope of this calculation is to: summarize applicable project requirements and codes relating to backfilling nonemplacement openings, removal of uncommitted materials from the subsurface, installation of drip shields, and erecting monuments; compile an inventory of boreholes that are found in the area of the subsurface repository; describe the magma bulkhead feature and location; and include figures for the proposed shaft and ramp seals. The objective of this calculation is to: categorize the boreholes for sealing by depth and proximity to the subsurface repository; develop drawing figures which show the location and geometry for the magma bulkhead; include the shaft seal figures and a proposed construction sequence; and include the ramp seal figure and a proposed construction sequence. The intent of this closure and sealing calculation is to support the License Application by providing a description of the closure and sealing methods for the Safety Analysis Report. The closure and sealing calculation will also provide input for Post Closure Activities by describing the location of the magma bulkhead. This calculation is limited to describing the final configuration of the sealing and backfill systems for the underground area. The methods and procedures used to place the backfill and remove uncommitted materials (such as concrete) from the repository and detailed design of the magma bulkhead will be the subject of separate analyses or calculations. Post
Closure and Sealing Design Calculation
International Nuclear Information System (INIS)
The purpose of the ''Closure and Sealing Design Calculation'' is to illustrate closure and sealing methods for sealing shafts, ramps, and identify boreholes that require sealing in order to limit the potential of water infiltration. In addition, this calculation will provide a description of the magma that can reduce the consequences of an igneous event intersecting the repository. This calculation will also include a listing of the project requirements related to closure and sealing. The scope of this calculation is to: summarize applicable project requirements and codes relating to backfilling nonemplacement openings, removal of uncommitted materials from the subsurface, installation of drip shields, and erecting monuments; compile an inventory of boreholes that are found in the area of the subsurface repository; describe the magma bulkhead feature and location; and include figures for the proposed shaft and ramp seals. The objective of this calculation is to: categorize the boreholes for sealing by depth and proximity to the subsurface repository; develop drawing figures which show the location and geometry for the magma bulkhead; include the shaft seal figures and a proposed construction sequence; and include the ramp seal figure and a proposed construction sequence. The intent of this closure and sealing calculation is to support the License Application by providing a description of the closure and sealing methods for the Safety Analysis Report. The closure and sealing calculation will also provide input for Post Closure Activities by describing the location of the magma bulkhead. This calculation is limited to describing the final configuration of the sealing and backfill systems for the underground area. The methods and procedures used to place the backfill and remove uncommitted materials (such as concrete) from the repository and detailed design of the magma bulkhead will be the subject of separate analyses or calculations. Post-closure monitoring will not
Agriculture-related radiation dose calculations
International Nuclear Information System (INIS)
Estimates of radiation dose to the public must be made at each stage in the identification and qualification process leading to siting a high-level nuclear waste repository. Specifically considering the ingestion pathway, this paper examines questions of reliability and adequacy of dose calculations in relation to five stages of data availability (geologic province, region, area, location, and mass balance) and three methods of calculation (population, population/food production, and food production driven). Calculations were done using the model PABLM with data for the Permian and Palo Duro Basins and the Deaf Smith County area. Extra effort expended in gathering agricultural data at succeeding environmental characterization levels does not appear justified, since dose estimates do not differ greatly; that effort would be better spent determining usage of food types that contribute most to the total dose; and that consumption rate and the air dispersion factor are critical to assessment of radiation dose via the ingestion pathway. 17 refs., 9 figs., 32 tabs
Agriculture-related radiation dose calculations
Energy Technology Data Exchange (ETDEWEB)
Furr, J.M.; Mayberry, J.J.; Waite, D.A.
1987-10-01
Estimates of radiation dose to the public must be made at each stage in the identification and qualification process leading to siting a high-level nuclear waste repository. Specifically considering the ingestion pathway, this paper examines questions of reliability and adequacy of dose calculations in relation to five stages of data availability (geologic province, region, area, location, and mass balance) and three methods of calculation (population, population/food production, and food production driven). Calculations were done using the model PABLM with data for the Permian and Palo Duro Basins and the Deaf Smith County area. Extra effort expended in gathering agricultural data at succeeding environmental characterization levels does not appear justified, since dose estimates do not differ greatly; that effort would be better spent determining usage of food types that contribute most to the total dose; and that consumption rate and the air dispersion factor are critical to assessment of radiation dose via the ingestion pathway. 17 refs., 9 figs., 32 tabs.
Calculating the Economic and Environmental Effects of Agricultural Production
DEFF Research Database (Denmark)
Skop, E.; Schou, J. S.
Projekt: Bæredygtige strategier i landbruget. Et tværfagligt forskningsprojekt med deltagelse af Statens Jordbrugsøkonomiske Institut, Statens Planteavlsforsøg, Statens Jordbrugstekniske Forsøg, Statens Husdyrsforsøg, Den Kgl. Veterinær- og Landbohøjskole og Danmarks Miljøundersøgelser....
TRANS-I: A fast calculating computer code for the calculation of reactivity transients
International Nuclear Information System (INIS)
In literature is shown that the adiabatic and the quasistatic approximation to space time neutron kinetics are generally fast and conservative methods for calculating reactivity transients. Nevertheless if a feedback reactivity is considered these methods predict too high values of peak flux, energy production and temperature. It is demonstrated, that the deficiency of adiabatic and quasistatic method can be removed, if the mean fuel temperature is multiplied by a weighting factor to get a corrected temperature for calculating Doppler-feedback. The code TRANS-I including this modification is presented. (author)
International Nuclear Information System (INIS)
Purpose: A number of techniques are available to determine the dosimetric impact of intrafraction motion during intensity modulated radiation therapy (IMRT). Motion-induced dose perturbations can be determined both computationally and experimentally using a number of different dosimetric metrics. However, these measures may lead to different conclusions regarding the clinical impact of motion. This study compares the analysis of identical dose perturbations using different dosimetric metrics. Calculated changes in target D95% are used as a reference. Methods: A total of 3768 motion-encoded dose distributions were calculated for nine lung tumor patients. The motion-encoded dose distributions were compared to static dose distributions using three dosimetric metrics: 2D γ, 3D γ, and histogram analysis. Each of these metrics was used to analyze dose perturbations both globally and within the target structure. Furthermore, the failing voxels were analyzed separately according to failure mode, i.e., under vs. over-dosed voxels. Metrics were evaluated based on their agreement with changes in target D95%. Evaluations included the metrics' maximum average sensitivity and specificity (MASS) in detecting unacceptable deliveries, a coefficient correlated to ranking (τ), and the linear correlation coefficient, r. Results: Of the evaluated metrics, the histogram metric restricted to the under-dosed voxels within the target agreed best with changes in target D95%. This metric achieved a MASS of 0.93, a τ of 0.69, and an r-value of 0.85. In comparison, the unrestricted 2D γ metric achieved MASS = 0.77, τ = 0.40, and r = 0.67. Restricting the 2D γ test both geographically and in failure mode increased the MASS to 0.85, τ to 0.70, and the r-value to 0.80. Conclusions: This study suggests that any clinical decisions based solely on an unrestricted 2D γ metric are suboptimal. A geographic and failure mode restriction can improve results. The remaining uncertainties with non
Practical astronomy with your calculator
Duffett-Smith, Peter
1989-01-01
Practical Astronomy with your Calculator, first published in 1979, has enjoyed immense success. The author's clear and easy to follow routines enable you to solve a variety of practical and recreational problems in astronomy using a scientific calculator. Mathematical complexity is kept firmly in the background, leaving just the elements necessary for swiftly making calculations. The major topics are: time, coordinate systems, the Sun, the planetary system, binary stars, the Moon, and eclipses. In the third edition there are entirely new sections on generalised coordinate transformations, nutr
Calculation of thermal diffuse scattering
Wakabayashi, N.; Nicklow, R. M.; Katano, S.; Ishii, Y.; Child, H. R.; Smith, H. G.; Fernandez-Baca, J. A.
We have developed a computer program to calculate the thermal diffuse scattering (TDS) intensity distribution for single-crystal specimens in a diffractometer with no energy analysis. We assumed that the phonon frequencies are approximated by those of elastic waves and that the elastic constants, density and lattice parameters of the system under study are known. The results of the calculations were compared to experimental data obtain for single crystals of Si, diamond and NiAl at the wide-angle neutron diffractometer (WAND) at the HFIR at Oak Ridge National Laboratory. Excellent agreement was found between the calculations and the experimental observations.
Calculation of thermal diffuse scattering
International Nuclear Information System (INIS)
The authors developed a computer program to calculate the thermal diffuse scattering (TDS) intensity distribution for single crystal specimens in a diffractometer with no energy analysis. They assumed that the phonon frequencies are approximated by those of elastic waves and that the elastic constants, density and lattice parameters of the system under study are known. The results of the calculations were compared to experimental data obtained for single crystals of Si, diamond and NiAl at the Wide Angle neutron Diffractometer at the HFIR at Oak Ridge National Laboratory. Excellent agreement was found between the calculations and the experimental observations
A simple method for calculating Clebsch-Gordan coefficients
Energy Technology Data Exchange (ETDEWEB)
Klink, W H; Wickramasekara, S, E-mail: william-klink@uiowa.ed, E-mail: wickrama@grinnell.ed, E-mail: s-wickram@uiowa.ed [Department of Physics and Astronomy, University of Iowa, Iowa City, IA 52242 (United States)
2010-09-15
This paper presents a simple method for calculating Clebsch-Gordan coefficients for the tensor product of two unitary irreducible representations (UIRs) of the rotation group. The method also works for multiplicity-free irreducible representations appearing in the tensor product of any number of UIRs of the rotation group. The generalization to representations with multiplicity is straightforward and briefly discussed.
Calculation of gas migration in fractured rock
International Nuclear Information System (INIS)
Calculations are presented for rock properties characteristic to the Forsmark area. The rock permeability was determined by flow tests in vertical boreholes. It is assumed that the permeability distribution obtained from these boreholes is representative also for the permeability distribution along the repository cavern. Calculations were worked out for two different types of boundary conditions, one in which a constant gas flow rate equivalent to a gas production of 33000 kg/year was assumed and the other in which a constant gas cushion of 0.5 metres was assumed. For the permeability distribution considered, the breakthrough at the sea bottom occurred within one hour. The gaswater displacement took place mainly through the fractures of high permeability and practically no flow took place in the fractures of low permeability. (orig./DG)
Calculation of baryon masses in quantum chromodynamics
International Nuclear Information System (INIS)
The polarization operator of quark currents with the baryon quantum numbers is considered in quantum chromodynamics. The non-zero mean vacuum of the field operator products are taken into account. The sum rules are obtained assuming that in the virtuality region approximately 1 GeV, among the mean vacuum values violating the chiral invariance, the most important is . Saturating these sum rules by the lowest baryonic states one is able to calculate the masses of the isobar Δ and nucleon N, Msub(Δ) 1.4 GeV, Msub(N) = 1 GeV, up to 15 % through the known value . The mass splitting in the baryonic decuplet Msub(Σ*) - Msub(Δ) = 125 MeV is calculated in the first order in the current strange quark mass msub(s) = 150 MeV. Certain results for that baryonic resonances have been obtained
ISSUES OF CIVIL REGULATION CALCULATIONS IN AGRICULTURE
Directory of Open Access Journals (Sweden)
Ulash Umarov
2014-05-01
Full Text Available One of the main sources of providing economic growth of agriculture and maintenance welfare life of population of Uzbekistan is required to develop step-by-step legislation. It regulates legal relations linked with calculations in agriculture and constantly its legal basis by virtue of theory, studies and principles of civil law according to the frames of reforms. The main goal of providing social-economic reforms in agriculture of Uzbekistan is to hardly continue maintaining successful life of country, and apropos of this increasing the size of producing in agriculture which based on competitive market, widening new range of production. Uninterruptedly continuing the strategy of economic reforms directed to provide successfully execution of governmental programs which aimed to develop diversified farm enterprise – studying legal problems of civil legal regulation of social-economic and investments relations play the main role based on calculations of current industry.
Microscopic Calculations In Diffractive Deep Inelastic Scattering
Pronyaev, A V
1999-01-01
New fundamental observables are becoming accessible with the Leading Proton Spectrometers (LPS) of ZEUS and H1. This enables us to test more thoroughly the pQCD mechanism of diffractive Deep Inelastic Scattering (DIS). Calculations of the diffractive cross-section in the small Bjorken x limit have been performed. We have used the microscopic QCD formalism of distractive DIS to find higher twist corrections to the transverse structure functions and predict the diffractive slope and azimuthal asymmetries. We establish duality correspondence between diffraction into low-mass continuum and vector meson production, and calculate the diffractive contribution to the spin structure functions.* *This work received partial support from the US DOE grant DE- FG02-96ER40994. --- 20 --- AN
Relativistic calculations of atomic structure
Fricke, Burkhard
1984-01-01
A review of relativistic atomic structure calculations is given with a emphasis on the Multiconfigurational-Dirac-Fock method. Its problems and deficiencies are discussed together with the contributions which go beyond the Dirac-Fock procedure.
Calculations of turbulent separated flows
Zhu, J.; Shih, T. H.
1993-01-01
A numerical study of incompressible turbulent separated flows is carried out by using two-equation turbulence models of the K-epsilon type. On the basis of realizability analysis, a new formulation of the eddy-viscosity is proposed which ensures the positiveness of turbulent normal stresses - a realizability condition that most existing two-equation turbulence models are unable to satisfy. The present model is applied to calculate two backward-facing step flows. Calculations with the standard K-epsilon model and a recently developed RNG-based K-epsilon model are also made for comparison. The calculations are performed with a finite-volume method. A second-order accurate differencing scheme and sufficiently fine grids are used to ensure the numerical accuracy of solutions. The calculated results are compared with the experimental data for both mean and turbulent quantities. The comparison shows that the present model performs quite well for separated flows.
Calculation method of Tesla coil
Коломієць, Роман Олександрович
2015-01-01
Tesla coil, despite the simplicity of its design may be called one of the least studied electronic devices. The article is an attempt to bring in various experimental results of general theoretical framework, which is the basis of exact calculation method of Tesla coils. Such calculation should be the starting point to create devices based on it. In order to develop such methods were considered the general principles of designing Tesla coil, reviewed the most famous mathematical models of its...
Hydraulic calculation of pressure pipes
Mikhalev, M. A.
2012-01-01
In the present time there is only one classic method for hydraulic calculation of pressure pipes. In it fluid flow velocity and pipeline diameter are considered as given values.The paper proposes a procedure for physical modeling and hydraulic calculation of pressure pipes, based on the theory of similarity. Methods for obtaining similarity criteria from combinations of similarity numbers were discussed. Similarity numbers and criteria and criteria equations were defined.
Multifragmentation calculated with relativistic forces
International Nuclear Information System (INIS)
A saturating hamiltonian is presented in a relativistically covariant formalism. The interaction is described by scalar and vector mesons, with coupling strengths adjusted to the nuclear matter. No explicit density dependence is assumed. The hamiltonian is applied in a QMD calculation to determine the fragment distribution in O + Br collision at different energies (50 - 200 MeV/u) to test the applicability of the model at low energies. The results are compared with experiment and with previous non-relativistic calculations. (orig.)
Enthalpy Calculation for Pressurized Oxy- coal Combustion
Weihong Wu; Jingli Huang
2012-01-01
Oxy-fuel combustion is recognizing one of the most promising available technologies that zero emission accomplishment may be in the offing. With coal burned under the pressure of 6MPa and oxygen-enriched conditions, the high temperature and high pressure gaseous combustion product is composed of 95% CO2 and water-vapor, with the rest of O2, N2 and so on. However, once lauded as classic approach of resolving fuel gas enthalpy calculation pertaining to ideal gas at atmospheric pressure was rest...
Calculation of 90Sr content in food
International Nuclear Information System (INIS)
The method presented was used to determine the 90Sr contamination of the samples from the agricultural products and foods under investigation by measuring the Sr fractions in two different time settings. Considering the decays from 89Kr to 89Y and from 90Kr to 90Zr as well as the respective half-lives, the activity sums of the 89Sr and 90Sr with significantly differing half-lives are used for the calculations. The resulting 90Sr/89Sr activity ratio of the sample shows the contamination life, too. A correction is needed for the equilibrium activity sum of 90Sr+90Y. (Sz.J.)
Quarkonium production at ATLAS
Price, D; The ATLAS collaboration
2011-01-01
The production of quarkonium is an important testing ground for QCD calculations. The J/psi and Upsilon production cross-sections are measured in proton-proton collisions at a centre-of-mass energy of 7 TeV with the ATLAS detector at the LHC. Differential cross-sections as a function of transverse momentum and rapidity are presented. The fraction of J/psi produced in B-hadron decays is also measured and the differential production cross-sections of prompt and non-prompt J/psi production determined separately. Results are compared to recent predictions from perturbative QCD calculations.
Ore reserve calculation methods used by Eldorado Nuclear Limited
International Nuclear Information System (INIS)
Uranium-bearing pitchblende deposits of the Beaverlodge area in northern Saskatchewan are highly complex. The ideas and concepts of ore reserve calculation methods employed by Eldorado Nuclear Limited in assessing and planning the mining of these deposits are described. A manual block-system of ore reserve calculation was used before the adoption of the current computerized system. Four classifications are used for ore reserves calculated by the system, which provides two main program jobs for calculating ore reserves and several additional ones that involve calculations and graphical presentation of ore reserve information for use in mine planning. A comparison of production statistics and ore reserve calculations illustrates the accuracy of the method. (author)
Conditions for industrial production
DEFF Research Database (Denmark)
Jensen, Karsten Ingerslev; Schultz, Jørgen Munthe; Brauer, H.
1996-01-01
The possibility of an industrial aerogel glazing production is discussed with respect to sample size, sales volume and prices. Different ways of an industrial assembling line is outlined and the total costs of a 1 square meter aerogel glazing is calculated.......The possibility of an industrial aerogel glazing production is discussed with respect to sample size, sales volume and prices. Different ways of an industrial assembling line is outlined and the total costs of a 1 square meter aerogel glazing is calculated....
A simple approximation of productivity scores of fuzzy production plans
DEFF Research Database (Denmark)
Hougaard, Jens Leth
2005-01-01
This paper suggests a simple approximation procedure for the assessment of productivity scores with respect to fuzzy production plans. The procedure has a clear economic interpretation and all the necessary calculations can be performed in a spreadsheet making it highly operational......This paper suggests a simple approximation procedure for the assessment of productivity scores with respect to fuzzy production plans. The procedure has a clear economic interpretation and all the necessary calculations can be performed in a spreadsheet making it highly operational...
Production of long-lived 26Al and 24Na from neutron interaction in Al target
International Nuclear Information System (INIS)
Precise estimate of radionuclide production in neutron induced reaction is important in the latest state-of-the art nuclear technology of Accelerator Driven Sub-critical Systems (ADSS). Deman of efficient running, optimized output and ensuring personnel safety in an ADSS have boosted the study of high energy neutron induced nuclide production, while target design and other logistic studies have revived interest in the study of same system at lower energies. In this paper we report the production cross section and yield of radionuclides formed in thick aluminum target by neutron induced reactions at 20 MeV and 100 MeV projectile energy. 27Al is a common element found in accelerator facility and this study provides data for radioactive waste generation for ADSS operation as well as radiotoxicity production in target studies. We have calculated the source term for production of nuclides in (n,2n), (n,α) reactions in the framework of nuclear reaction model codes ALICE, EMPIRE and TALYS, and estimated the total yield. Our calculated results are compared with experimental data wherever available. Our analysis shows that production of the long-lived 26Al is well predicted by EMPIRE and TALYS while ALICE largely underpredicts the data in the energy range of 1-20 MeV. (author)
Calculation system for physical analysis of boiling water reactors
International Nuclear Information System (INIS)
Although Boiling Water Reactors generate a quarter of worldwide nuclear electricity, they have been only little studied in France. A certain interest now shows up for these reactors. So, the aim of the work presented here is to contribute to determine a core calculation methodology with CEA (Commissariat a l'Energie Atomique) codes. Vapour production in the reactor core involves great differences in technological options from pressurised water reactor. We analyse main physical phenomena for BWR and offer solutions taking them into account. BWR fuel assembly heterogeneity causes steep thermal flux gradients. The two dimensional collision probability method with exact boundary conditions makes possible to calculate accurately the flux in BWR fuel assemblies using the APOLLO-2 lattice code but induces a very long calculation time. So, we determine a new methodology based on a two-level flux calculation. Void fraction variations in assemblies involve big spectrum changes that we have to consider in core calculation. We suggest to use a void history parameter to generate cross-sections libraries for core calculation. The core calculation code has also to calculate the depletion of main isotopes concentrations. A core calculation associating neutronics and thermal-hydraulic codes lays stress on points we still have to study out. The most important of them is to take into account the control blade in the different calculation stages. (author)
Methods of core neutronic calculation
International Nuclear Information System (INIS)
Core neutronic calculations lead to the determination of geometry, composition, controls systems and to the core exploitation limits in agreement with the expected performances, with safety rules, technological choices and fuel management methods. Neutronic calculations object are described with physics justifications of hypothesis and approximations. A description and a definition of reactivity and power distribution are also given. A panorama of calculation methods used in the conception of fast breeder and pressure water reactors, are described with numerical aspects and general interest considerations related to the field of these methods and to the industrial options chosen. A complete industrial uses panorama of methods derived from the classical or generalized perturbation theory is followed by the qualification and the definition of the validity field of numerical codes.(A.B.). 88 refs., 6 figs
Insertion device calculations with mathematica
Energy Technology Data Exchange (ETDEWEB)
Carr, R. [Stanford Synchrotron Radiation Lab., CA (United States); Lidia, S. [Univ. of California, Davis, CA (United States)
1995-02-01
The design of accelerator insertion devices such as wigglers and undulators has usually been aided by numerical modeling on digital computers, using code in high level languages like Fortran. In the present era, there are higher level programming environments like IDL{reg_sign}, MatLab{reg_sign}, and Mathematica{reg_sign} in which these calculations may be performed by writing much less code, and in which standard mathematical techniques are very easily used. The authors present a suite of standard insertion device modeling routines in Mathematica to illustrate the new techniques. These routines include a simple way to generate magnetic fields using blocks of CSEM materials, trajectory solutions from the Lorentz force equations for given magnetic fields, Bessel function calculations of radiation for wigglers and undulators and general radiation calculations for undulators.
PHEBUS-FPTO Benchmark calculations
International Nuclear Information System (INIS)
This report summarizes a set of pre-test predictions made for the first Phebus-FP test, FPT-O. There were many different calculations, performed by various organizations and they represent the first attempt to calculate the whole experimental sequence, from bundle to containment. Quantitative agreement between the various calculations was not good but the particular models in the code responsible for disagreements were mostly identified. A consensus view was formed as to how the test would proceed. It was found that a successful execution of the test will require a different operating procedure than had been assumed here. Critical areas which require close attention are the need to devize a strategy for the power and flow in the bundle that takes account of uncertainties in the modelling and the shroud conductivity and the necessity to develop a reliable method to achieve the desired thermalhydraulic conditions in the containment
Parameters calculation of shielding experiment
International Nuclear Information System (INIS)
The radiation transport methodology comparing the calculated reactions and dose rates for neutrons and gama-rays, with experimental measurements obtained on iron shield, irradiated in the YAYOI reactor is evaluated. The ENDF/B-IV and VITAMIN-C libraries and the AMPX-II modular system, for cross sections generation collapsed by the ANISN code were used. The transport calculations were made using the DOT 3.5 code, adjusting the boundary iron shield source spectrum to the reactions and dose rates, measured at the beginning of shield. The neutron and gamma ray distributions calculated on the iron shield presented reasonable agreement with experimental measurements. An experimental arrangement using the IEA-R1 reactor to determine a shielding benchmark is proposed. (Author)
Canister Transfer Facility Criticality Calculations
Energy Technology Data Exchange (ETDEWEB)
J.E. Monroe-Rammsy
2000-10-13
The objective of this calculation is to evaluate the criticality risk in the surface facility for design basis events (DBE) involving Department of Energy (DOE) Spent Nuclear Fuel (SNF) standardized canisters (Civilian Radioactive Waste Management System [CRWMS] Management and Operating Contractor [M&O] 2000a). Since some of the canisters will be stored in the surface facility before they are loaded in the waste package (WP), this calculation supports the demonstration of concept viability related to the Surface Facility environment. The scope of this calculation is limited to the consideration of three DOE SNF fuels, specifically Enrico Fermi SNF, Training Research Isotope General Atomic (TRIGA) SNF, and Mixed Oxide (MOX) Fast Flux Test Facility (FFTF) SNF.
The Monte Carlo calculation of gamma family
International Nuclear Information System (INIS)
The method of the Monte Carlo calculation for gamma family was investigated. The effects of the variation of values or terms of parameters on observed quantities were studied. The terms taken for the standard calculation are the scaling law for the model, simple proton spectrum for primary cosmic ray, a constant cross section of interaction, zero probability of neutral pion production, and the bending of the curve of primary energy spectrum. This is called S model. Calculations were made by changing one of above mentioned parameters. The chamber size, the mixing of gamma and hadrons, and the family size were fitted to the practical ECC data. When the model was changed from the scaling law to the CKP model, the energy spectrum of the family was able to be expressed by the CKP model better than the scaling law. The scaling law was better in the symmetry around the family center. It was denied that primary cosmic ray mostly consists of heavy particles. The increase of the interaction cross section was necessary in view of the frequency of the families. (Kato, T.)
Enthalpy Calculation for Pressurized Oxy- coal Combustion
Directory of Open Access Journals (Sweden)
Weihong Wu
2012-08-01
Full Text Available Oxy-fuel combustion is recognizing one of the most promising available technologies that zero emission accomplishment may be in the offing. With coal burned under the pressure of 6MPa and oxygen-enriched conditions, the high temperature and high pressure gaseous combustion product is composed of 95% CO2 and water-vapor, with the rest of O2, N2 and so on. However, once lauded as classic approach of resolving fuel gas enthalpy calculation pertaining to ideal gas at atmospheric pressure was restrained by pressure limitations. In this paper, the flue gas was assumed by an ideal mixture of four real gases system, and the equations for calculating the flue gas enthalpy were derived by using the cofunction method incorporating with the Dalton’s law of pressure summation based on the Virial equation. Consequently, the results showed that the calculation method on the basis of the Dalton’s law of pressure summation appears to be a reasonable enthalpy values for the 6MPa oxygen-enriched coal combustion as opposed to the inferior cofunction method.
RTP: Radionuclides inventories calculation using ORIGEN Code
International Nuclear Information System (INIS)
ORIGEN is a widely used computer code for calculating the buildup, decay, and processing of radioactive materials. The ORIGEN code was created by famous and reputable nuclear institution in United States, Oak Ridge National Laboratory (ORNL). For a nuclear reactor, either it is a nuclear power reactor or nuclear research reactor, the radionuclide inventories data is important. This data is acquired by performing source term modelling. A fresh nuclear fuel could not cause any harm to human. However, used nuclear fuel could pose danger threat to human. The fission products particularly long-lived radionuclides for example H-3, Co-60, Cs-137 that are generated inside the fuel yield a significance amount of radioactivity. Therefore, there is no doubt that for a facility having a nuclear reactor, it is vital to anticipate the amount of fission products inside the fuel together with the radioactivity that it may emit. Sufficient information on the radionuclide inventories allows the facility to provide adequate shielding protection and ensure safe transportation of nuclear fuel, when it is needed. This paper briefly describes application of ORIGEN code to calculate the radionuclides inventories of TRIGA-PUSPATI REACTOR (RTP) fuel. (author)
Ab Initio Calculations of Oxosulfatovanadates
DEFF Research Database (Denmark)
Frøberg, Torben; Johansen, Helge
1996-01-01
Restricted Hartree-Fock and multi-configurational self-consistent-field calculations together with secondorder perturbation theory have been used to study the geometry, the electron density, and the electronicspectrum of (VO2SO4)-. A bidentate sulphate attachment to vanadium was found to be stable...... with anO-V-O angle of 72.5 degrees . The calculated spectrum shows bands in reasonable agreement with anexperimental spectrum which has been attributed to (VO2SO4)-. The geometry and the electron density fortwo binuclear vanadium complexes proposed as intermediates in the vanadium catalyzed SO2...
Data Acquisition and Flux Calculations
DEFF Research Database (Denmark)
Rebmann, C.; Kolle, O; Heinesch, B;
2012-01-01
In this chapter, the basic theory and the procedures used to obtain turbulent fluxes of energy, mass, and momentum with the eddy covariance technique will be detailed. This includes a description of data acquisition, pretreatment of high-frequency data and flux calculation.......In this chapter, the basic theory and the procedures used to obtain turbulent fluxes of energy, mass, and momentum with the eddy covariance technique will be detailed. This includes a description of data acquisition, pretreatment of high-frequency data and flux calculation....
Friction and wear calculation methods
Kragelsky, I V; Kombalov, V S
1981-01-01
Friction and Wear: Calculation Methods provides an introduction to the main theories of a new branch of mechanics known as """"contact interaction of solids in relative motion."""" This branch is closely bound up with other sciences, especially physics and chemistry. The book analyzes the nature of friction and wear, and some theoretical relationships that link the characteristics of the processes and the properties of the contacting bodies essential for practical application of the theories in calculating friction forces and wear values. The effect of the environment on friction and wear is a
Molecular calculations with B functions
Steinborn, E O; Ema, I; López, R; Ramírez, G
1998-01-01
A program for molecular calculations with B functions is reported and its performance is analyzed. All the one- and two-center integrals, and the three-center nuclear attraction integrals are computed by direct procedures, using previously developed algorithms. The three- and four-center electron repulsion integrals are computed by means of Gaussian expansions of the B functions. A new procedure for obtaining these expansions is also reported. Some results on full molecular calculations are included to show the capabilities of the program and the quality of the B functions to represent the electronic functions in molecules.
Thermodynamic Calculations for Systems Biocatalysis
DEFF Research Database (Denmark)
Abu, Rohana; Gundersen, Maria T.; Woodley, John M.
2015-01-01
‘Systems Biocatalysis’ is a term describing multi-enzyme processes in vitro for the synthesis of chemical products. Unlike in-vivo systems, such an artificial metabolism can be controlled in a highly efficient way in order to achieve a sufficiently favourable conversion for a given target product...
Foreign Acquisition, Wages and Productivity
DEFF Research Database (Denmark)
Bandick, Roger
This paper studies the effect of foreign acquisition on wages and total factor productivity (TFP) in the years following a takeover by using unique detailed firm-level data for Sweden for the period 1993-2002. The paper takes particular account of the potential endogeneity of the acquisition...... no effects on overall, skilled or less-skilled wage growth neither in targeted Swedish MNEs nor in targeted Swedish non-MNEs and neither if the acquisition was motivated by vertical or horizontal motives. However, the results indicate that both targeted Swedish MNEs and non-MNEs have better growth in...
Foreign Acquisition, Wages and Productivity
DEFF Research Database (Denmark)
Bandick, Roger
2011-01-01
This paper studies the effect of foreign acquisition on wages and total factor productivity (TFP) in the years following a takeover by using unique detailed firm-level data for Sweden for the period 1993-2002. The paper takes particular account of the potential endogeneity of the acquisition...... no effects on overall, skilled or less-skilled wage growth neither in targeted Swedish MNEs nor in targeted Swedish non-MNEs and neither if the acquisition was motivated by vertical or horizontal motives. However, the results indicate that both targeted Swedish MNEs and non-MNEs have better growth in...
Estonian oil shale resources calculated by GIS method
International Nuclear Information System (INIS)
A digital map of Estonian oil shale mining was created for joining the data about technological, environmental, and social limitations in the deposit. For evaluating potential resource of oil shale, based on borehole database, its amount, tonnage and energy were calculated. Thereafter the quantity of economical oil shale for power plants and shale oil resource were calculated. Energy rating is the most important factor for determining oil shale reserves in the case of using it for electricity generation. In the case of oil production, data on oil yield and potential resources in oil shale are the most important figures to determine the value of the deposit. Basing on the models, oil resource has been calculated. Resource data can be used for composing master plans for the deposit considering both power generation and oil production. The data can be also used for composing development plans of mines and for logistics calculations. (author)
ITER Port Interspace Pressure Calculations
Energy Technology Data Exchange (ETDEWEB)
Carbajo, Juan J [ORNL; Van Hove, Walter A [ORNL
2016-01-01
The ITER Vacuum Vessel (VV) is equipped with 54 access ports. Each of these ports has an opening in the bioshield that communicates with a dedicated port cell. During Tokamak operation, the bioshield opening must be closed with a concrete plug to shield the radiation coming from the plasma. This port plug separates the port cell into a Port Interspace (between VV closure lid and Port Plug) on the inner side and the Port Cell on the outer side. This paper presents calculations of pressures and temperatures in the ITER (Ref. 1) Port Interspace after a double-ended guillotine break (DEGB) of a pipe of the Tokamak Cooling Water System (TCWS) with high temperature water. It is assumed that this DEGB occurs during the worst possible conditions, which are during water baking operation, with water at a temperature of 523 K (250 C) and at a pressure of 4.4 MPa. These conditions are more severe than during normal Tokamak operation, with the water at 398 K (125 C) and 2 MPa. Two computer codes are employed in these calculations: RELAP5-3D Version 4.2.1 (Ref. 2) to calculate the blowdown releases from the pipe break, and MELCOR, Version 1.8.6 (Ref. 3) to calculate the pressures and temperatures in the Port Interspace. A sensitivity study has been performed to optimize some flow areas.
On calculation of photoneutron yields
International Nuclear Information System (INIS)
A simple analytical expression has been obtained for the photon track lengths in the region of nuclei giant resonance by summing the cross-sections of the bremsstrahlung from thin layers. The photoneutron yields from thick Cu and Pb targets calculated for verifying this expression are in a good agreement with the experimental results obtained by other authors
Dead reckoning calculating without instruments
Doerfler, Ronald W
1993-01-01
No author has gone as far as Doerfler in covering methods of mental calculation beyond simple arithmetic. Even if you have no interest in competing with computers you'll learn a great deal about number theory and the art of efficient computer programming. -Martin Gardner
Sparsifying preconditioner for soliton calculations
Lu, Jianfeng; Ying, Lexing
2016-06-01
We develop a robust and efficient method for soliton calculations for nonlinear Schrödinger equations. The method is based on the recently developed sparsifying preconditioner combined with Newton's iterative method. The performance of the method is demonstrated by numerical examples of gap solitons in the context of nonlinear optics.
Relativistic multiple scattering Xα calculations
International Nuclear Information System (INIS)
A one component relativistic theory has recently been developed and tested on isolated atoms and on molecules through the molecular scattered-wave formalism of Johnson, while its application to energy-band calculations (through a relativistic augmented-plane-wave program) has also been considered
CALCULATION OF MAGNETIC OIL CLARIFIER
Puzik, S. O.; National Aviation University; Shevchuk, V. S.; National Aviation University; Baranivskiy, Y. O.; National Aviation University; Mykhailenko, O. O.; National Aviation University
2013-01-01
Technology of oil cleaning from iron-containing impurities that shows the feasibility of magnetic cleaners applying was investigated. Comparative analysis of the types of magnetic clarifier was carried out. Procedure of calculating the dimension type of oil clarifier, which makes it possible to obtain high purity grade oil, was offered.
Sparsifying preconditioner for soliton calculations
Lu, Jianfeng
2015-01-01
We develop a robust and efficient method for soliton calculations for nonlinear Schr\\"odinger equations. The method is based on the recently developed sparsifying preconditioner combined with Newton's iterative method. The performance of the method is demonstrated by numerical examples of gap solitons in the context of nonlinear optics.
Giavitto, Jean-Louis; Reichenmann, François
2012-01-01
Alan Turing a non seulement défini l'objet d'étude de l'informatique, le calcul, mais aussi révolutionné notre rapport aux machines. Il a fondé l'informatique comme un domaine scientifique autonome et a ouvert le chemin vers un nouveau continent à explorer et à habiter.
Professional Growth & Support Spending Calculator
Education Resource Strategies, 2013
2013-01-01
This "Professional Growth & Support Spending Calculator" helps school systems quantify all current spending aimed at improving teaching effectiveness. Part I provides worksheets to analyze total investment. Part II provides a system for evaluating investments based on purpose, target group, and delivery. In this Spending Calculator…
Prenatal radiation exposure. Dose calculation
International Nuclear Information System (INIS)
The unborn child requires special protection. In this context, the indication for an X-ray examination is to be checked critically. If thereupon radiation of the lower abdomen including the uterus cannot be avoided, the examination should be postponed until the end of pregnancy or alternative examination techniques should be considered. Under certain circumstances, either accidental or in unavoidable cases after a thorough risk assessment, radiation exposure of the unborn may take place. In some of these cases an expert radiation hygiene consultation may be required. This consultation should comprise the expected risks for the unborn while not perturbing the mother or the involved medical staff. For the risk assessment in case of an in-utero X-ray exposition deterministic damages with a defined threshold dose are distinguished from stochastic damages without a definable threshold dose. The occurrence of deterministic damages depends on the dose and the developmental stage of the unborn at the time of radiation. To calculate the risks of an in-utero radiation exposure a three-stage concept is commonly applied. Depending on the amount of radiation, the radiation dose is either estimated, roughly calculated using standard tables or, in critical cases, accurately calculated based on the individual event. The complexity of the calculation thereby increases from stage to stage. An estimation based on stage one is easily feasible whereas calculations based on stages two and especially three are more complex and often necessitate execution by specialists. This article demonstrates in detail the risks for the unborn child pertaining to its developmental phase and explains the three-stage concept as an evaluation scheme. It should be noted, that all risk estimations are subject to considerable uncertainties.
Threshold singularities, dispersion relations and fixed-order perturbative calculations
Beneke, Martin
2016-01-01
We show how to correctly treat threshold singularities in fixed-order perturbative calculations of the electron anomalous magnetic moment and hadronic pair production processes such as top pair production. With respect to the former, we demonstrate the equivalence of the "non-perturbative", resummed treatment of the vacuum polarization contribution, whose spectral function exhibits bound state poles, with the fixed-order calculation by identifying a threshold localized term in the four-loop spectral function. In general, we find that a modification of the dispersion relation by threshold subtractions is required to make fixed-order calculations well-defined and provide the subtraction term. We then solve the apparent problem of a divergent convolution of the partonic cross section with the parton luminosity in the computation of the top pair production cross section starting from the fourth-order correction. We find that when the computation is performed in the usual way as an integral of real and virtual cor...
Calculation of driling and blasting parameters in blasting performance
Dambov, Risto; Karanakova Stefanovska, Radmila; Dambov, Ilija
2015-01-01
In all mining technology drilling and blasting parameters and works are one of the main production processes at each mine. The parameters of drilling and blasting and explosives consumption per ton of blasting mass are define economic indicators of any blasting no matter for what purpose and where mining is performed. The calculation of rock blasting should always have in mind that the methodology of calculation of all drilling and blasting parameters in blasting performance are performed for...
Calculating Profit: A Historical Perspective on the Development of Capitalism
Toms, Steven
2008-01-01
The paper introduces the notion of different methods of calculating and analysing profitability as signatures of capitalism at different stages of development. Interactions between the development of the productive forces and the socialisation of capital ownership jointly impact on these signatures, such that profit calculations are historically contingent. These interactions take the identification of capitalism beyond simple associations with the presence or absence of double-entry bookkeep...
Calculation of 14 MeV neutron transmission
International Nuclear Information System (INIS)
The possibility of using the 28 group constant system (28-GCS) for calculating the transport of neutrons with initial energy of 14 MeV in thermonuclear reactor blankets is studied. A blanket project suggested by the Oak Ridge National Laboratory is used as a test version to estimate applicability of the 28-GCS. Niobium is used in a blanket as a structural material. A mixture of lithium nuclides is used for tritium production. The results of blanket test calculation and the calculational results obtained using the 28-GCS from the UKNDL library are compared. The numerical 28-group calculation of blonket is carried out by means of the ROZ-6 and ROZ-9 codes but not by the Monte-Carlo method as compared with the test calculation. Time of the blanket calculation on the BESM-6 computer by means of the ROZ-9 code in 2P5 approximation using the 28-GCS amounts to 10 min. It is noted that to create effective codes for the numerical blanket calculation different calculational grids are necessary for different energy grups. The calculations carried out have shown the possibility of using the 28-group library of cross sections for the numerical solution of the neutron transport equation in estimating analysis of blankets
Calculation of radioactive species transport in a TRIGA reactor
Energy Technology Data Exchange (ETDEWEB)
Mladin, Daniela, E-mail: daniela.mladin@nuclear.ro [Institute for Nuclear Research, Campului, 1, Mioveni 115400, Arges (Romania); Mladin, Mirea, E-mail: mirea.mladin@nuclear.ro [Institute for Nuclear Research, Campului, 1, Mioveni 115400, Arges (Romania); Toma, Alexandru, E-mail: alexandru.toma@nuclear.ro [Institute for Nuclear Research, Campului, 1, Mioveni 115400, Arges (Romania); Dulama, Cristian, E-mail: cristian.dulama@nuclear.ro [Institute for Nuclear Research, Campului, 1, Mioveni 115400, Arges (Romania); Prisecaru, Ilie, E-mail: prisec@cne.pub.ro [University “Politehnica” of Bucharest, Power Engineering Faculty, Nuclear Power Plants Department, Splaiul Independentei 313, Sector 6, Bucharest (Romania); Covaci, Stefan, E-mail: bebecus@yahoo.com [Institute for Nuclear Research, Campului, 1, Mioveni 115400, Arges (Romania)
2013-09-15
Highlights: • We created a TRIGA facility model with CATHARE2. • We calculated a source of fission products in postulated accident conditions. • We calculated the source of Ar-41 during reactor normal operation. • We modeled the transport and release of fission products and Ar-41 at reactor stack. • Steady-state experimental Ar-41 volumetric activity is compared with the calculated activity. -- Abstract: The objective of the paper is to develop and use a model for radioactive species transport in the primary circuit and in the reactor hall of the Romanian TRIGA facility. CATHARE2 V25 code (Code for Analysis of Thermal–Hydraulics during an Accident of Reactor and Safety Evaluation) is used. CATHARE is developed by the French Atomic Energy Commission (CEA) and owned in partnership with three other French partners: EDF, AREVA-ANP and IRSN. The radio-chemical components in CATHARE2 include, besides activation products, four fission products with predefined characteristics (Kr-87, Xe-133, I-131, Cs-137). New radioactive species can be defined by the user, and the characteristics of the existing ones can be modified. The TRIGA model created comprises both the primary reactor circuit and reactor hall, involving water zones and non-condensable gas (air). Ventilation system is simulated by means of boundary conditions. Using the same facility model, two separate studies are performed with externally calculated sources: -fission product species transport and evacuation. This is done as PSA support studies, postulating core damage and volatile species release; -Ar-41 transport and evacuation. Argon activity at reactor stack is calculated for normal operation and compared to monitor readings. The paper describes also the calculation of the radioactive sources based on SCALE 4.4 in case of fission products, and using MCNP5 for Ar-41.
AGING FACILITY CRITICALITY SAFETY CALCULATIONS
International Nuclear Information System (INIS)
The purpose of this design calculation is to revise and update the previous criticality calculation for the Aging Facility (documented in BSC 2004a). This design calculation will also demonstrate and ensure that the storage and aging operations to be performed in the Aging Facility meet the criticality safety design criteria in the ''Project Design Criteria Document'' (Doraswamy 2004, Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''SNF Aging System Description Document'' (BSC [Bechtel SAIC Company] 2004f, p. 3-12). The scope of this design calculation covers the systems and processes for aging commercial spent nuclear fuel (SNF) and staging Department of Energy (DOE) SNF/High-Level Waste (HLW) prior to its placement in the final waste package (WP) (BSC 2004f, p. 1-1). Aging commercial SNF is a thermal management strategy, while staging DOE SNF/HLW will make loading of WPs more efficient (note that aging DOE SNF/HLW is not needed since these wastes are not expected to exceed the thermal limits form emplacement) (BSC 2004f, p. 1-2). The description of the changes in this revised document is as follows: (1) Include DOE SNF/HLW in addition to commercial SNF per the current ''SNF Aging System Description Document'' (BSC 2004f). (2) Update the evaluation of Category 1 and 2 event sequences for the Aging Facility as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004c, Section 7). (3) Further evaluate the design and criticality controls required for a storage/aging cask, referred to as MGR Site-specific Cask (MSC), to accommodate commercial fuel outside the content specification in the Certificate of Compliance for the existing NRC-certified storage casks. In addition, evaluate the design required for the MSC that will accommodate DOE SNF/HLW. This design calculation will achieve the objective of providing the criticality safety results to support the preliminary design of the Aging
MOx benchmark calculations by deterministic and Monte Carlo codes
International Nuclear Information System (INIS)
Highlights: ► MOx based depletion calculation. ► Methodology to create continuous energy pseudo cross section for lump of minor fission products. ► Mass inventory comparison between deterministic and Monte Carlo codes. ► Higher deviation was found for several isotopes. - Abstract: A depletion calculation benchmark devoted to MOx fuel is an ongoing objective of the OECD/NEA WPRS following the study of depletion calculation concerning UOx fuels. The objective of the proposed benchmark is to compare existing depletion calculations obtained with various codes and data libraries applied to fuel and back-end cycle configurations. In the present work the deterministic code NEWT/ORIGEN-S of the SCALE6 codes package and the Monte Carlo based code MONTEBURNS2.0 were used to calculate the masses of inventory isotopes. The methodology to apply the MONTEBURNS2.0 to this benchmark is also presented. Then the results from both code were compared.
Fuel depletion calculation in MTR-LEU NUR reactor
Directory of Open Access Journals (Sweden)
Zeggar Foudil
2008-01-01
Full Text Available In this article, we present the results of a few energy groups calculations for the NUR reactor fuel depletion analysis up to 45 000 MWd/tU taken as the maximum fuel burn up. The WIMSD-4 cell code has been employed as a calculation tool. In this study, we are interested in actinides such as the uranium and plutonium isotopes, as well as fission products Xe-135, Sm-149, Sm-151, Eu-155, and Gd-157. Calculation results regarding the five energy groups are in a good agreement with those obtained with only two energy groups which can, therefore, be used in all subsequent calculations. Calculation results presented in this article can be used as a microscopic data base for estimating the amount of radioactive sources randomly dispersed in the environment. They can also be used to monitor the fuel assemblies inventory at the core level.
Detailed Burnup Calculations for Testing Nuclear Data
Leszczynski, F.
2005-05-01
A general method (MCQ) has been developed by introducing a microscopic burnup scheme that uses the Monte Carlo calculated fluxes and microscopic reaction rates of a complex system and a depletion code for burnup calculations as a basis for solving nuclide material balance equations for each spatial region in which the system is divided. Continuous energy-dependent cross-section libraries and full 3D geometry of the system can be input for the calculations. The resulting predictions for the system at successive burnup time steps are thus based on a calculation route where both geometry and cross sections are accurately represented, without geometry simplifications and with continuous energy data, providing an independent approach for benchmarking other methods and nuclear data of actinides, fission products, and other burnable absorbers. The main advantage of this method over the classical deterministic methods currently used is that the MCQ System is a direct 3D method without the limitations and errors introduced on the homogenization of geometry and condensation of energy of deterministic methods. The Monte Carlo and burnup codes adopted until now are the widely used MCNP and ORIGEN codes, but other codes can be used also. For using this method, there is need of a well-known set of nuclear data for isotopes involved in burnup chains, including burnable poisons, fission products, and actinides. For fixing the data to be included in this set, a study of the present status of nuclear data is performed, as part of the development of the MCQ method. This study begins with a review of the available cross-section data of isotopes involved in burnup chains for power and research nuclear reactors. The main data needs for burnup calculations are neutron cross sections, decay constants, branching ratios, fission energy, and yields. The present work includes results of selected experimental benchmarks and conclusions about the sensitivity of different sets of cross
Calculation of potassium critical temperature
International Nuclear Information System (INIS)
The paper describes the algorithm of the functional prediction which is based on the selforganization of nonlinear algebraic models. The calculation procedure includes the module for the recognition of the dependence type hitch allows to restrict the number of choice of the prediction functions at the each step of the model building. The characteristic property of this algorithm is bootstrap method application as the external criteria of the selforganization. The calculation module is built using APL*PLUS and the user-friendly interface is implemented using Clipper 5.01 under Windows control. When using the algorithm and the programs, the critical point of potassium has been predicted on the base of the solubility curves of liquid and steam. 9 refs.; 1 fig.; 1 tab